ML20080E196
| ML20080E196 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/19/1983 |
| From: | Cooper W TELEDYNE ENGINEERING SERVICES |
| To: | Harold Denton, Maneatis G, Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V), Office of Nuclear Reactor Regulation, PACIFIC GAS & ELECTRIC CO. |
| Shared Package | |
| ML16340D655 | List: |
| References | |
| 5511-495, NUDOCS 8308300794 | |
| Download: ML20080E196 (135) | |
Text
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'RTELEDYNE ENGINEERING SERVCES 130 SECOND AVENUE WALTHAM MASSACHUSETTS 02254 (617) 890-3350 TWX (7101324 7508 August 19, 1983 5511-495 Mr. G. A. Maneatis, Executive Vice-President Pacific Gas and Electric Co.
77 Beale Street San Francisco, California 94106 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nucl*ar Regulatory Comission Washington, D. C. 20555 i
Mr. J. B. Martin, Regional Administrator Region V U. S. Nuclear Regulatory Comission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Re: Docket No. 50-275, OL-DPR-76 Diablo Canyon Unit 1
Subject:
IDVP Final Report - Eighth Text Submittal q
Gentlemen:
In response to the Comission Order and Staff Letter which established the DCNPP-1 Independent Design Verification Program, TES as IDVP Program Manager provides the eighth text submittal of the IDVP Final Report.
Attachment 1 to this letter sumarizes information which became available on August 18-19th, af ter the revisions were prepared. Such items will be fully incorporated in any future revisions.
Since various Open Items and E01 Files have been resolved, certain pages of the Final Report are no longer applicable. The following pages should be deleted.
Table 5-4-1003 Revision 0 Table 5-4-1022 Revision 0 Enclosed is the following revised text.
Page xi Revision 1 Page xii Revision 1 Page 4.4.2-7 Revision 1 Page 4.4.3-1 Revision 1 0 Page Page Page 4.4.3-3 4.4.3-4 4.4.5-3 Revision 1 Revision 1 Revision 1 h.
v' v Page 4.4.6-1 Revision 1 '
Page 4.4.6-4 Revision 1 F308300794 830826 Page gnginggggg,$ETALLL i on 1 PDR ADOCK 05000275 R PDR j
l Messrs. Maneatis, Denton, Martin f,9",5j19'1983 "n'TELEDYNE ENGINEERING SERVICES o Page 4.5.2.3-6 Revision 1 o Page 4.5.2.3-10 Revision 1 Page 4.5.3.2-7 Revision 1 Page 4.5.3.2-8 Revision 1 Page 4.5.3.2-9 Revision 1 Page 4.6.2.2-1 Revision 1 Page 4.6.2.2-2 Revision 1 Page 4.6.2.2-3 Revision 1 Page 4.6.3-3 Revision 2 Page 4.6.3-4 Revision 1 Page 4.6.3-5 Revision 1 Page 4.6.4.3-1 Revision 1 Page 4.6.4.3-2 Revision 1 Page 4.6.4.3-3 Revision 0 Page 4.6.5.2-1 Revision 1 Page 4.6.5.2-2 Revision 1 Page 4.6.6.2-2 Revision 1 Page 4.6.6.3-1 Revision 1 Page 4.6.6.3-3 Revision 1 Page 4.6.7-3 Revision 1 Page 4.6.7-4 Revision 1 Page 4.6.7-5 Revision 1 Page 4.6.8.2-3 Revision 1 Page 4.6.8.2-4 Revision 1 Page 4.6.9-1 Revision 1 Page 4.6.9-2 Revision 1
(,,)
Page 4.8.5-2 Revision 1 Page 5.2-2 Revision 2 page 5.2-3 Revision 2 Table 5-1-1003 Revision 2 Table 5-1-1022 Revision 2 Table 5-1-1069 Revision 1 Table 5-1-1092 Revision 2 Table 5-2-1124 Revision 1 Table 5-3-1069 Revision 1 Page 6.4.3-1 Revision 1 Page 7.4-1 Revision 1 Page 7.4-2 Revision 1 Table 7.4-1 (2 pgs) Revision 1 Page 8.1.1-1 Revision 1 Page 8.1.2-2 Revision 1 Page 8.1.2-3 Revision 1 Page 8.1.4-1 Revision 1 Page 8.1.4-2 Revision 1 Page 8.1.4-3 Revision 1 Page 8.2.1-1 Revision 1 Page 8.2.1-2 Revision 1 Page 8.2.2-1 Revision 1 Page 8.2.2-2 Revision 1 Page D.3-5 Revision 1 Page 0.5-9 Revision 1 8 Page Page Page D.3-19 0.3-26 D.3-27 Revision 1 Revision 1 Revision 1 Page D.3-33 Revision 1 Page D.3-34 Revision 1 i
l 1
ssrs. aneatis, Denton, Martin ,
Pa e 3 ENGINEERING SERVICES rs
() Page Page D.3-49 D.3-61 Revision 2 Revision 2 Page D.3-70 Revision 2 Page D.3-71 Revision 2 Page D.3-72a Revision 2 Page D.3-72b Revision 2 Page D.3-72c Revision 2 Page D.3-72d Revision 0 Page D.3-73 Revision 1 Page D.3-77 Revision 1 Page D.3-ll8 Revision 2 Page E.1-1
- Revision 1 Page E.1-2 Revision 2 Page E.1-3 Revision 3 Page E.1-4 Revision 3 Page E.1-5 Revision 2 Page E.2A-2 Revision 1 Page E.2A-3 Revision 2 Page E.2A-4 Revision 1 Page E.28-1 Revision 2 Page E.28-2 Revision 2 Page E.2B-3 Revision 3 Page E.3A-2 Revision 2 Page E.3B-1 Revision 2 Page F.1-1 Revision 1 O ease Page F t-2 F.1-3 Revision 1 Revision 1 Page F.1-4 Revision 0 The text submitted by this letter is considered to be cowlete, except as specifically indicated.
Very truly yours, TELEDYNE cNGINEERING SERVICES William E. Cooper 9-Project Manager - 5511 WEC:cfr Enclosures cc: H. E. Schierling (NRC) (85)
R. R. Fray (PGandE) (30 + 220)
E. Denison (RLCA) (6)
R. F. Reedy (RFR) (6)
F. Sestak (SWEC) (10)
M. J. Strumwasser, Esq.
D. F. Fleischaker, Esq.
(U) J. Reynolds, Esq/J. R. Phillips, Esq.
B. Norton, Esq.
A. C. Gehr, Esq.
R. B. Hubbard J. Roesset
WTF1 FnYNE ENGINEERING SERVICES O
ATTACHMENT 1 TO TES LETTER 5511-495 The revision pages transmitted by this letter reflect changes in IDVP completion status through Wednesday, August 17, 1983. Additional ITRs have been issued and E01 actions taken on August 17-18th which are sumarized by this attachment.
- 1. ITRs Issued:
ITR-59, Corrective Action - Stress in Large Bore Piping.
ITR-60, Corrective Action - Large and Small Bore Piping.
ITR-63, Corrective Action - HVAC Ducts, Raceways, Instrument Tubing, and Supports.
- 2. E0I File Actions:
983: Closed with issuance of ITR-63, Revision 0.
1143: Opened to identify that excessive loads exist on an HVAC support anchor bolt.
n 3009: Opened to ' identify a potential concern regarding the V containment interior structure horizontal design response spectra.
- 3. Based on the actions identified above, Table 7.4-1 has been updated as indicated by the next two attached pages.
- 4. The remaining pages of this attachment have been provided by the DCP to update the information included in Section 7.3 of the IDVP Final Report.
O r
t "RTELEDYNE ENGINEERING SERVICES
()
TABLE 7.4-1 STATUS OF INCOMPLETE VERIFICATIONS DEFINED BY ITRs-8 AND -35 AS OF AUGUST 19, 1983 Report Subsections Verification Complete?
Unresolved ITR IOVP PGandE E01s No.* Field Design Mod 4.4.2.2 2.1.2 1097 55 Yes No NA 4.4.3 2.1.3 1092 57-1 NA Yes No 4.4.4 2.1.1 1014 54 NA No No 3009 4.4.5 2.1.1.4.3 1014 51 Yes No No 4.4.6 2.1.5 58-1 Yes Yes NA 4.4.8 2.1.4 1026 56 Yes No No 1028 4.5.2.3a 2.2.1 938 59-1 Yes Part No
,, 1098 (m- ) 1138 1741 4.5.2.3b 2.2.3 1098 60-1 Yes Part No 4.5.3.2a 2.2.2 1098 61 Yes Part NA 1141 4.5.3.2b 2.2.2 1098 60-1 Yes Part No 1142 4.6.2.2 2.3.1 67-1 NA Yes NA 4.6.3 2.3.1 67-1 NA Part NA 4.6.4 2.3.1 67-1 Yes Part NA
,4.6.5 2.3.1 67-1 Yes Part NA
- When the ITR number is followed by another number, the ITR has been issued but a further revision is expected.
8 1 of 2
. . . . . _ . . , . . . . . . . . . _ . .. . . _ . . ~
i "MTr:rrVNE ENGINEERING SERVICES
(~} TABLE 7.4-1 (Cont) v Report Subsections Verification Complete?
Unresolved ITR IOVP PGandE E01s _ No.* Field Design Mod 4.6.6.3 2.3.3 67-1 Yes Yes NA 4.6.6.5 2.5 1134 63-1 No Part No 1143 4.6.7 2.3.2 67-1 Yes Yes NA 4.6.8.lb 2.4 63-1 Yes Yes No 4.6.8.2b 2.6 63-1 Yes Yes NA 4.6.9 NA NA 67-1 Yes Yes NA 4.9.1.4 2.3.2.3.3 NA 67-1 NA Yes NA 4.9.2 NA NA 68 Yes No NA 4.9.3 NA NA 65 No No No O
- When the ITR number is followed by another number, the ITR has been issued but a further revision is expected.
0 2 of 2 6 i..- - . . . . . . . _ . _ . . . . . . . . . . . . . . -.........._..i... ..-i-J
DIABLO CANYON PROJECT 0 90 %
PHASE I STATUS O Au2ust 12, 1983 uPd ate
SUMMARY
In the following we are provided a listing of the status of our Phase I work.
We have presented below the scope of the DCP CAP as defined in the Phase I Final Report. This is an update of the July 26, 1983 transmittal, DCVP-TES-1271.
This sumary is divided into 3 sections, providing a status of the work for Phase I.
Section 1. Civil / Structural Work Section 2. Piping and Pipe Supports Design Review Section 3. Equipment Seismic Design Review For each section come of the information is presented in tables. The status of all information is in terms of the percent of the work that is complete.
Where no percentage are shown, no DCP activity has occurred. Complete back-up information is available in the Phase I Final Report.
O O
August 12, 1983 00400/0116P
SECTION 1. CIVIL / STRUCTURE WORK b
O The status of the Civil / Structural work is sumarized below. Details on the status of this work are presented in Table 1.1 which includes fraportant information contained in the footnotes to this table. For details on this work, please see applicable sections of the Phase I Final Report.
O O
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SECTION 2. PIPING AND PIPE SUPPORTS DESIGN REVIEW O 2.i taroe sore Pi ,in.
General - The Final Report Scope, Criteria and Methodology sections are complete and no changes are anticipated. Analyses and qualification of installations assigned to Westinghouse Corporation have been completed.
All current criteria and design input data have been transmitted to Westinghouse. They have reviewed recent changes to certain input data and anticipate no further modifications to be required. This estimate includes iterations due to construction interface and as-built review.
Table 2.1 tabulates the status of this information.
All large bore piping has been reviewed and qualified. However, certain calculations exist with inputs identified as preliminary or results which O require review and acceptance. The notes to the table describe items which require closure of documentation and an assessment of ea:h item's significance. These items should not be totaled as an indication of analyses with open items as many analyses contain more than a single item.
A small number of iterations of pipe analyses may also result from problems encountered during support design review and redesign associated with recently issued analyses and construction difficulties encountered during support or pipe modification.
Thirty-eight minor pipe modifications have been issued to date and construction has completed thirty-five. 4 O
August 12, 1983 00400/0116P
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1 r tr e n t e o art r e u a c f tos r g c
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O e ai on pn ot e l o 1 x 3 O LP o o o o Na Sa Lir Fl [ e A O 8 9
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2.2 Small Bore Piping I
O All small bore piping associated with both the Generic and Sample Programs has been reviewed and qualified with a few exceptions (Table 2.2) . In addition, certain calculations exist with- inputs identified as preliminary or results which require review and acceptance by others.
The notes to the table describe a listing of items which require closure of documentation or completion of a calculation activity. The significance of each item is addressed.
Some computer analyses may require revision due to possible future changes in input data such as spectra or header movements.
A small number of iterations of pipe analyses may also result from problems encountered during support design review and redesign associated with recantly issued analyses and construction difficulties encountered during support or pipe modification.
Ten pipe modifications have been issued and construction is complete.
O August 12, 1983 00400/Oll6P
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Ns / / 0/ / / / / /
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M a . .
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R N P o de d .
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2.3 Large Bure Supports O All large bore piping supports have been reviewed and qualified.
However, iterations of piping analyses due to input data revision are causing support requalification and redesign (Table 2.3). Presently 1430 supports out of a total of 4300 require requalification due to piping analysis revision. The bulk of these supports are associated with decreased loads and movements and require only documentation changes. In addition the activities and items described in the notes must be completed to ensure no further calculation or design revision. For each item an assessment of significance is established.
1035 supports are in the construction process. 2600 are installed and are accepted through QC inspection and as-built preparation.
O O
August 12, 1983 C0400/0116P 9
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l 2.4 Small Bare Pipe Suppsrts
(
Q All small bore supports associated with both the Generic and Sample programs have been reviewed and qualified (Table 2.4). However, iterations of piping analyses due to input revisions and changes to spectra and temperatures and operating modes are causing support review and redesign. Presently, approximately 49 supports out of 2500 require requalification due to these changes. Very few modifications are expected to result from this effort. In addition, support qualification / design iterations will occur as described in the notes to the table. The significance of each item is addressed.
One hundred fifty supports are in the construction process. 1500 are installed.
O l
0 August 12, 1983 0040D/0116P
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SECTION 3. EQUIPMENT SEISMIC DESIGN The status of the equipment seismic design work is presented in the Q
following. This includes Mechanical Equipment, Electrical Equipment and Instruments, and Heating, Ventilating, and Air Conditioning (HVAC) Equipment.
3.1 Mechanical Equipment The scope, criteria, and methodology phases of the program are 100%
complete. For 100% of the mechanical equipment, calculations which determine if the equipment is seismically qualified for a given set of controlled seismic input have been competed (See Table 3-1).
3.2 Instrumentation and Controls The IAC work consists of selected analysis, design, and construction activities. The status for all I and C equipment is presented in Table 3-1.
For the analysis work completion means, the equipment qualification levels have been compared to the appropriate required responsa spectra and have been found acceptable. Some final documentation may be outstanding.
Design work is complete when the DCN has been issued by engineering for modifications to bring equipment up to the qualified configuration.
O August 12, 1983 0040D/0116P
O Construction or* is comPiete hea aii eaut meat P modificatioas have beea completed by General Construction. Some final documentation may be outstanding.
For Instrument tubing supports the analyses are complete as of March 29,1983 (Rev. 6 of DCM C-17), and the design and construction resulting frcmi these analyses are complete.
3.3 Electrical Equipment Activities relating to Phase I are complete. Responses have been provided to all RFIs and EDIs.
4 O Section 2.3.2 of the Phase I Final Report provides the detailed infomation for the Class IE electrical equipment.
- 3.4 HVAC Equipment The review of seismic qualification of Class I HVAC equipment has been completed as of August 16, 1983. This is based upon the application of seismic spectra issued for project use. Table 3.1 tabulates the percent completeness of major steps of the related ork.
August 12, 1983 00400/0116P
The se< > ic 9 ai s tication or Hv4C e,o,,.ent ,, an on,,,,, ,,,,,,, ,,
O which the analyses will be updated as new input are generated in accordance with PEI-13 and DCM CH-52.
O O
\ August 12, 1983 0040D/0116P i
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1%'F WE ENGNEERING SEFMCES IDVP FINAL REPORT LIST OF TABLES FOLLOWS TABLE TITLE PAGE N0.
5-3-932 Modification in Response to Specific Error 5.4.2-1 E01 File: 932 5-3-938 Modification in Response to Specific Error E0I File: 938 5-3-949 Modification in Response to Specific Error 5.4.2-1 E01 File: 949 5-3-963 Modification in Response to Specific Erro_r 5.4.2-1 E01 File: 963 5-3-1069 Modification in Response to Specific Error 5.4.2-1 E0I File: 1069 5-3-1107 Modification in Response to Specific Error 5.4.2-1 E01 File: 1107 5-3-8009 Modification in Response to Specific Error b E0I File: 8009 5.4.2-1 5-3-8010 Modification in Response to Specific Error E01 File: 8010 5.4.2-1~
5-3-8012 Modification in Response to Specific Error E01 File: 8012 5.4.2-1 5-3-8017 Modification in Response to Specific Error E0I File: 8017 5.4.2-1 5-3-8057 Modification in Response to Specific Error E01 File: 8057 5.4.2-1 5-3-8062 Modification in Response to Specific Error E0I File: 8062 5.4.2-1 5-4-983 Modification in Response to Generic Concern 5.4.2-1 E0I File: 983 g
5-4-1014 Modification in Response to Generic Concern 5.4.2-1 E01 File: 1014 O
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IDVP FINAL REPORT LIST OF TABLES FOLLOWS TABLE TITLE PAGE N0.
5-4-1026 Modification in Response to Generic Concern 5.4.2-1 E01 File: 1026 5-4-1092 Modification in Response to Generic Concern E01 File: 1092 5.4.2-1 5-4-1098 Modification in Response to Generic Concern E01 File: 1098 5.4.2-1 5-4-8009 Modification in Response to Generic Concern E01 File: 8009 5.4.2-1 5-4-8057 Modification in Response to Generic Concern E01 File: 8057 5.4.2-1 7.3-1 Phase I Corrective Action Program Status:
Ci~il v Structural 7.3.3-1 g 7.3-2 Phase I Corrective Action Program Status:
O Large Bore Piping 7.3.3-1 7.3-3 Phase I Corrective Action Program Status:
Small Bore Piping 7.3.3-1 7.3-4 Phase I Corrective Action Program Status:
Large Bore Supports 7.3.3-1 7.3-5 Phase I Corrective Action Program Status:
Small Bore Pipe Supports 7.3.3-1 7.3-6 Phase I Corrective Action Program Status:
Equipment Seismic Design 7.3.3-1 '
7.4-1 Status of Incomplete Verifications Defined by ITRs-8, -34, and -35 7.4-4
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where necessary to assess the effects of various DCP assumptions and calculations. For the auxililary building, the IDVP performed separ-ate analyses, such as sensitivity studies for the dynamic models, to assess the significance of modeling parameters.
Two E01s were written as a result of the IDVP verification:
E01 1124 was issued for the finite element modeling of the con-trol room floor slab. The location of the supporting walls in the model did not match the actual locations. This model was used to generate Hosgri floor response spectra. The DCP has corrected this error. The IDVP then verified that slab quali-fication analyses for vertical loading were acceptable. This E0I was classified as a Class B Error, and the error resolved by verification of the DCP reanalysis.
O E0I 1132 was issued because the Auxiliary Building DCP member evaluations had been reported as being complete. This file was combined with E01 1097. The DCP is still in the process of evaluating the slabs for in-plane loads, and this effort is subject to further verification.
The verification program intended to be conducted by the IDVP is not yet completed. Based upon the efforts performed to June 25, 1983, the IDVP considers the following aspects of the DCP work to be acceptable and to satisfy the licensing criteria:
Y e Qualification analyses reflect the as-built structure.
e Accidental eccentricities for the concrete portions were applied properly.
e The synthetic time-histories used for analyses give an
() acceptable representation of the smooth design spectra.
IDVP 4.4.2-7 REV1 FINAL 830816
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(] 4.4.3 Fuel Handling Building The Fuel Handling Building (FHB) is a Design Class I steel-framed structure which is supported at elevation 140 feet of the auxiliary building. The building dimensions are 58 feet (E-W direction) by 366 feet (N-S direction) by 48 feet high. It supports a fuel handling bridge crane and houses other equipment. Moment-resisting steel frames 'in the East-West direction and cross-braced columns in the North-South direction comprise the structural system. The roof is a trussed and cross-braced diaphragm covered with metal decking and built-up roofing. A portion of the end frames in the East-West direc-tion are supported on a concrete wall common with the fan rooms.
In accordance' with the FSAR and Hosgri report, Design Class I struc-tures must be' qualified for all seismic events; thus, member evalua-tion for the structural steel members was performed for the DE, DDE, and Hosgri events and the required loading combinations.
O V
4.4.3.1 Verification of Corrective Action The IDVP verification of the D' ? Corrective Action Program for the FHB is defined in ITRs-8 and -35. The IDVP verification consisted of examining on a sampling basis the analyses for both seismic and non-seismic loads. The seismic loads are the DE, DDE, and Hosgri events, while the non-siesmic loads are dead, live, wind, temperature, etc.
The IDVP will perform a field inspection of the FHB when modifications are complete. Connections, additional members and/or removed members, etc., will be examined and checked for conformance with the design and qualification analyses. ITR-57 reports on the IDVP' verification of the FHB.
l The DCP conducted its evaluation of the criteria implementation and qualification analyses through the Internal Technical Program (ITP).
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V e Time history analyses (Hosgri) of the dynamic models which
. produced response spectra and provided accelerations for use in the equivalent static model. The input time history from elevation 140 feet of the auxiliary building was also reviewed.
e Evaluation of the nodal accelerations used to determine equivalent static loads.
e Computation of loads for the equivalent static analysis i l
and a sample of the computer runs for a static analysis I load case.
e Comparison of selected member loads with member allowables loads for the postulated Hosgri event.
O wJ The selected sample covers approximately 50% of the structure dynamic analyses, excluding the crane, and the same percentage for the static analysis and member evaluation. The IDVP did not review the prelim-l inary static model, which was used by the DCP as a. basis for determin-ing analysis and modification requirements.
4 No E0Is were issued for the FHB with regard to the DCP Corrective Action Program.
The verification program intended. to be conducted by the IDVP is com-plete except that the as-built condition will be field verified against the design drawings used as the basis for the analyses. Based upon the efforts performed to August 19, 1983, the IDVP considers the following aspects of the DCP work to be acceptable and to satisfy the licensing criteria:
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IDVP 4.4.3-3 REV1 FINAL 830816
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() e Omission of an allcwance for accidental eccentricity in the FHB because the torsional effects are accounted for in the auxiliary building response at elevation 140 feet.
e The ranges of crane locations and assessment of their effects upon results, e~ The dynamic models used in the FHB evaluation.
e Response spectra generation.
e Equivalent static loads determined from the dynamic accel-eration profiles. l l
e Qualification of members and connections.
() The IDVP intends to formulate final conclusions as to the qualifica-tion of the FHB and conformance to licensing criteria when the DCP modifications'and field walkdown have been completed and the IDVP has verified the as-built against the design conditions. This verifi-cation will be reported in Revision 1 to ITR-57. E01 1092 will not be closed until this field verification is complete.
(To Be Supplemented) 3 (a
IDVP 4.4.3-4 REV 1 FINAL 830816
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( The review of the PGandE model resulted in two areas of concern. .The first had to do with the frame consolidation used to obtain the equiv-alent radial beam flexural rigidity properties. The IDVP concluded that the frame consolidation does not adequately represent the struc-ture at elevations 101 and 106 feet.
/
The second concern was that th'e P andZ model does not consider the possible effects of tangential beam flexibility on local response spectra. The 10VP studies included simple one and two degrees-of- ,
t' i -freedom lumped mass models which confirmed that the tangential beam flexibility is an important factor in the respcnse spectra generation.
The results and conclusions of the verification' review of the contain-ment annulus has been reported in ITR-50. The conclusions relative to the specfic concerns of the NRC letter are:
l e There are no significant differences in the computed
(
{.f l
masses aad member joints (with the exception of the BNL error in the slab .to crane wall connection mentioned) be-tween the 1981/1982 URS/Blume analyses and BNL . (Model B)
' analysis. _
e Tlie joint characteristics in the Blume analysis realistic-ally represent the as-built configuration.
I e The spectra smoothing technique applied by PGandE is con-
'sistent with the DCNPP licensing criteria.
e Th issue of discrepancies between design pi ip ng analyses
, a'nd. the ' as-built configurations is' a generic concern that
< 'his been ident'ified by the IOVP and is discussed in 4.5.2.
e The significance of the errors in the modeling of bends in annulus structure piping is considered negligible.
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() 4.4.6 Intake Structure
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The intake structure is a massivelDesign Class II concrete structure that houses the Design C1 ass .I Ausiliary Saltwater (ASW) Pumps. The
' vhnt shaft and snorkel pipes, as well as nearby supporting equipment, s
athjartoftheASWt9 stem. The dynamic analysis of the Intake Struc-ture produces responsa~ spectra used as input to these systems.
i ~
s
\' s In -acccedance with the FSAR, a Desigr. Class II ' structure is required
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k retain,its integrity during a seismic event so that the function of
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Is Class I e % ment will not be impaired.
Hence, the DCP has evaluated o the structural integrity of the intake structure for the postulated s .
y ,
s Hosgr0 event, but floor rdsponse spectr a used for evaluation of safety-related 'equipent nave been comouted for DE, DDE and Hosgri t.
conditions.
O n
" 4 61 verificatioa or corrective Actioa Th IDVP verification of the' DCP Corrective Action Program for the in-take structure is defined in ITks-8 and -35. The IDVP review con-sisted of examining the qualificatiorc of the structure for seismic and ndn-seismic loads. The seismic loads are the DE, DDE, and Hosgri
', e events, while the non-seismic loads are soil bearing pressures, hydro-y dynamic, wave force, dea'd and live load, and missile loads. ITR-58 e ,
reports the IDVP verification ofi corrective action for the intake 3
~
structure. _
, The DCP reviewed the as-built drawings to ensure an accurate input to 7
the analysis and made modifications as necessary, as detailed in the PGandE Phase I Final Report. For the intake structure, the DCP re-s viewed and accepted the ~ dynamic analysis, member evaluation, genera-t' ion of response spectra, and structural stability calculations per-S formed by URS/ John Blume Associates. In addition, the Blume Internal fl, y
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e The flow straighteners possessed adequate strength using the ductility criteria specified. Walls and slabs were qualified without the use of ductility considerations.
o Vent shaft system was shown to be adequate.
As noted by the above statements and by consideration of the DCP qual-ification analyses, the IDVP considers the intake structure to be qualified and to meet licensing requirements. The sliding, over-turning and soil bearing pressure calculations are under continuing review as discussed in 4.9.2, and will be reported in ITR-68 and in Revision 1 to ITR-58.
(To Be Supplemented)
O o
LJ IDVP 4.4.6-4 REV 1 FINAL 830816
"MTri m(NE ENGINEERING SERVICES reviews, specific areas of interest were chosen for re-(]
views. These specific areas included items such as valve modeling and qualification, application of stress intensi-fication factor, spectra inputs, etc. Alternate calcula-tions were performed by the IDVP as necessary to review DCP calculations.
As a result of the above-described activity, four E01s were issued. E01 1126 addresses the SIF discrepancy for
. intermediate butt welds and the omission of a SIF of 1.9 at valve / elbow interfaces. This item has been incorpor-ated into the DCP final review checklist for review of potential impacts on all DCP analyses, and the file has been closed.
2 E0I 1133 addresses the discrepancy noted for one DCP valve model where only two-thirds of the required eccentric mass p
was considered in the DCP analysis. This item has been determined to be a Class C Error and has been resolved through revision of the DCP analysis.
E0I 1135 addresses the discrepancies in valve body . and operator weights for valves LCV-113 and -116. This item has been determined to be a Class C Error and resolved through revision of DCP analysis.
E01 1137 addresses a discrepancy in valve weight for FCV-365. This E01 together with E0Is 1133 and 1135 combined to form a generic concern with valve modeling. The item has been incorporated into the DCP Final Review checklist for review of potential impacts on all DCP analyses. The concern of EGI 1137 was determined to be a Class C Error.
The verification program intended to be conducted by the p IDVP is not yet complete. Based 'upon the efforts IDVP 4.5.2.3-4 REV1 FINAL 830816 l
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V performed to August 15, 1983, the IDVP considers the l following aspects of the DCP work to be acceptable and to satisfy the licensing criteria.
e The DCP reanalysis of all original work and ~ the development of the DCP final review checklist is an appropriate program for qualification of all DCP analyses.
e Qualification analyses in general reflect the as-built conditions.
e Overall modeling methods were found acceptable, except for application of stress intensification factors (SIF) and valve modeling as noted above, e Loadings used in the DCP analyses were found acceptable. Loading data were found properly con-Q trolled and applied by the DCP.
e Internal documentation was found to be in sufficient detail to allow the verification of transfer of data.
Computer files and descriptions were indexed.
e Stress analyses were found acceptable for all review-ed analyses except Analyses 2-111, Revision 0, and 4A-100, Revision 0, which contained unique discrep-ancies and were reanalyzed by the DCP.
e Numerical accuracy of the calculations sampled was adequate.
In summary, the IDVP concluded that DCP is following established procedures and licensing criteria, and is meeting the latest loading criteria and operating modes.
The concerns on stress intensification factors and valve modeling were determined to be generic concerns. These O
v IDVP 4.5.2.3-5 REV1 FINAL 830816
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generic concerns are resolved by the inclusion of specific checks in the DCP final review checklist. Certain valve models and SIFs will be reviewed by the IDVP after they have passed the DCP final review. None of the specific concerns that led to these two generic concerns caused an exceedence of the licensing criteria. The DCP Corrective Action Program for Design Class I large bore piping adequately covers all essential steps required to obtain proper qualification of the piping.
The IDVP intends to formulate a final conclusion as to the I
qualification of large bore piping and its conformance to licensing criteria when the IDVP verification is completed.
(To Be Supplemented)
- b. Large Bore Piping Supports The IDVP verification of the DCP Corrective Action Program for large bore pipe supports is defined in ITRs -8 and -
- 35. The IDVP review consisted of an examination of quali-fication of each pipe support for all seismic and non-seismic loads. Seismic loads are the DE, DDE, and Hosgri events, while non-seismic loads are deadload, thermal accident, friction, fast valve closure, and relief valve opening thrust. This activity will be reported in ITR-60.
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U criteria and accuracy of calculations. The process by which the IDVP selected support samples included the following:
e In general, the selected supports were associated with piping that was part of the IDVP large bore pip-ing sample.
o Several supports were selected as a result of IDVP field verification activities for piping samples, e The DCP General Pipe Support Status (GPSS) log was reviewed to determine revision status, respective piping analyses, etc. This status log listed approx-imately 6000 to 7000 supports.
e Supports were selected to represent various support U types, pipe sizes, plant locations, and organizations (consultants) performing design analyses.
The IOVP selected a total of 22 support analyses for re- l view. The support types were as follows:
e 3 snubbers e 6 spring hangers e 6 anchors e 7 rigid supports l The IDVP performed design reviews for the selected DCP analyses to verify the following aspects of the design g analysis:
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IDVP 4.5.2.3-8 REV1 FINAL 830818
W F W NE ENGNEERING SERVCES O performed a finite element analysis which applied the piping spectra to this support and demonstrated that criteria were satisfied. The IDVP has verified this analysis and E01 1122 was resolved as a Deviation. The IDVP does not consider it a generic concern.
E01 1129 notes that errors were made in calculating the weld stress for a 1/4-inch weld between pipe lug and supporting steel on Pipe Support 56S/3A. These errors offset each other and no overstress occurred. This item has.been classified as an error Class C. This E01 does not represent a generic concern.
E0I 1131 notes that the design analyses for Pipe Supports 58S/16V and 63/26V do not evaluate the shear lugs and attachment welds, as required in the DCP Corrective Action Program. The DCP has revised these analyses to include
{j the shear lugs and attachment welds. The IDVP review of the revised DCP calculations shows these stresses to be small. This E0I has been classified as a deviation.
The verification program intended to be conducted by the IDVP is not yet complete. Based upon the efforts performed to June 25, 1983, the IDVP considers the following aspects of the DCP work to be acceptable and to satisfy the licensing criteria.
e Support drawings are satisfactory.
e Loads and load combinations used in the pipe support analyses are correct.
e Pipe support frequencies are satisfactory (except as noted 'n E01 1122).
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'A V I W NE ENGNEERNG SERVICES f) v A design review checklist was developed for the IDVP re-view to ensure that all necessary items were examined and documented. Checklist observations were further expanded with comments where clarification or more det' ailed con-sideration was appropriate. In addition to the checklist, the IDVP design review included asessments of the com-pleteness, applicability, and consistency of the DCP review and reanalysis methodology.
The IDVP performed an analysis package and pipe ' support review to evaluate the completeness of all pertinent design input data, output results and associated documen-tation.
Alternate calculations were performed by the IDVP, where necessary, to assess the effects of various DCP assump-O tions end to confirm ceicuietions.
The IDVP selected a sample of 8 DCP small bore pipe l support analyses to ensure conformance to DCP criteria and accuracy of calculations. The selection process included the following:
e The DCP list of small bore supports that com-prised the full DCP review sample (approximately 210 supports) was reviewed by the IDVP.
e Supports were selected to represent various support types, pipe sizes, plant locations, and organizations (consultants) performing design analyses.
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O e In general, the selected supports were associat-ed with piping that was part of the IDVP small bore piping sample.
e Several supports were selected as a result of IDVP field verification activities for piping samples.
One E01 report was issued. E0I 1039 was classified as a Class C error because of an error in the DCP support deflection evaluation. The DCP revised their analysis to show support met criteria.
The verification program intended to be conducted by the IDVP is not yet complete. Based upon the efforts perform-ed to August 19, 1983, the IDVP considers the following l n aspects of the DCP work to be acceptable:
U l
e The small bore pipe supports analyzed by the DCP adequately represent the worst cases for the issues / design considerations determined by their
( generic and sampling reviews.
l e Support drawings are satisfactory.
e Pipe support drawings and information used in the analyses reflect the as-built conditions.
e Loads and load combinations used in the pipe support analyses are correct.
e Standard component supports such. as spring hangers, snubbers, and pipe clamps are satis-o t ; factory.
IDVP 4.5.3.2-8 REV1 FINAL 830818
W TAFrWNE ENGNEERNG SERVICES i O e All eight analyses meet criteria. l The IDVP intends to formulate a final conclusion as to the qualification of small bore pipe supports and their ' con-formance to licensing criteria when the IDVP verification has been completed. l l
(To Be Supplemented)
O IDVP 4.5.3.2-9 REV 1 FINAL 830818
l i
W Tri m(NE ENGINEERING SERVICES o
V 4.6.2.2 Verification of DCP Activities The IDVP verification of DCP work on tanks is defined by ITRs -8 and
-35. The IDVP verification of the DCP work includes all aspects described in Section 4.6.1 and the following aspects were emphasized:
e Verification of the PGandE review methodology to assure that the correct spectra were check'ed by PGandE against qualification analyses.
e Completeness of qualification The results of the verification have been reported in ITR-67. l
- The DCP Internal Technical Program for equipment consisted of a review of the seismic qualification, implemented by checking the latest O seismic qu lification d ta against those used for the qualification of equipment. This check used the latest response spectra for the DE, DDE, and Hosgri event. Whenever changes to the response spectra required requalification of the equipment, the equipment was requali-fied by analysis or testing. Equipment identified for review was that associated with the engineered safety systems designed by PGandE (Reference PGandE Phase I Final Report).
The CCW surge tank was selected as the IDVP verification sample of the DCP implementation. The CCW surge tank is a Design Class I tank and is located atop the auxiliary building at elevation 163 feet. This tank is classified and built to ASME Section VIII (Rules for Construc-tion of Pressure Vessels). This is one of five mechanical tanks reviewed by the DCP. Of the five, three were verified for Hosgri
~ loadings as part of the initial sample. Of the two remaining tanks, only the CCW sur ce tank was required to be evaluated for both DE and DDE loadings.
(J3 IDVP 4.6.2.2-1 REV1 FINAL 830816
"RTri FrVNE ENGINEERING SERVICES h The IOVP performed a design review for the OCP reanalysis. A check-list was developed which covered all required criteria items, and critical analytical procedures, ard ensured completeness of the IOVP review. In addition to the checklist, the IOVP review included assessments of the completeness, applicability, consistency, and adequacy of the OCP review and reanalysis methodology. Where discrep-ancies were noted, or methodology was deemed not totally appropriate, alternate calculations were carried out by the IOVP to verify the con-clusions of the DCP reanalysis.
The IDVP issued E0I 1136 which noted that the DCP analysis for the CCW surge tank calculated bolt shear stress allowables that did not con-form to established DCP criteria and the ASME code. However, the bolt stresses remain below the correct allowable values. The DCP analysis also did not consider internal pressure induced stress in the tank for the evalu'ation of tank stresses at the nozzle. Tank stresses would
,, exceed the specified allowable stress if pressure was considered using U the same values and procedures as the OCP analysis. However, it was determined that the DCP reanalysis was very conservative and the actual pressure stresses were negligible. Thus, actual total stresses were below criteria and E01 1136 was determined to be a Class C Error.
The technical aspects of the verification program conduc'ted by the IOVP has been completed and reported in ITR-67. Based upon these effortt, the IOVP considers the following aspects of the OCP work to be acceptable and to satisfy the licensing criteria:
e The seismic spectra utilized by the DCP for tanks reflects the current spectra.
s The mathematical modeling used in the reanalysis was con-sidered to be acceptable. '
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IOVP 4.6.2.2-2 REV1 FINAL 830818
"RTA m(NE ENGNEERING SERVCES O - ^11 estabiisaea oce criterie are coasiaered to neve beea l
adequately met.
The items identified in E01 1135 are considered to be random analytical discrepancies.
The IOVP intends to formulate a final conclusion as to the qualifica-tion of all mechanical equipment and its conformance to licensing criteria when all IOVP verification work in this area is complete.
Effects of future revisions to seismic spectra and piping nozzle loads on equipment remain to be evaluated as part of the IOVP completion sample.
(To Be Supolemented)
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IDVP 4.6.2.2-3 REV 1 FINAL 830818
W Tn m(NE ENGINEERING SEFNICES The one observation, E01 File 950, was the result of a discrepancy in (a) stiffener plate thickness determined from the field verification.
Although the IDVP did not consider physical modifications of FCV-95 to De necessary to satisfy criteria, the DCP modified all valves specified in DC0-G-M-876 by replacing a 3/8" thick plate with a plate of the 1/2" design thickness. The IDVP verified these modifications.
No additional sampling or verification of valves was required.
4.6.3.2 Verification of DCP Activities The IDVP performed verification of DCP activities for Valves in ac-cordance with ITRs-8 and -35. The IDVP examined the DCP work for all aspects discussed in Section 4.6.1. The results of this verification have been reported in ITR-67.
l The DCP Internal Technical Program (ITP) for Valves is closely tied to O the DCP efforts for piping. Certain valves were selected by the DCP for reanalysis to determine valve natural frequencies and allowable accelerations. These valves had been originally qualified by seismic service-related contractors to PGandE. Only motor-operated valves with eccentric masses were reanalyzed. The allowable acceler ation results were then used by piping to determine if modifications to the valve or pipe supporting structure were required.
Electro-Hydraulic Valve LCV-110 was selected as the IDVP verification sample. The valve is a Design Class I level control valve located on the pipeway structure outside the containment building. LCV-110 is one of the 6 different types of valves analyzed as part of the DCP's ITP.
LCV-110 is one of four similar valves: LCV-110, 111,113 and 115.
This type of valve was selected for the IDVP review sample because a similar valve had caused an overstress condition in the pipe line in IDVP 4.6.3-3 REV 2 FINAL 830816
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WF WE ENGNEERING SEFMCES 3
(V one of the IDVP initial sample piping analyses (Reference E01 1069).
In addition, the actuator motor on these valves had been replaced.
The IDVP performed a design review of DCP reanalysis. A checklist was deveioped which covered all criteria items, critical analytical pro-cedures, and completeness of the DCP reanalysis. In addition to the checklist, the IDVP design review included reviewer assessments on the completeness, applicability, consistency and adequacy of the DCP re-analysis methods. Where discrepancies were noted, or methods deemed' not totally appropriate, alternate calculations were carried out by the IDVP to verify the conclusions of the DCP. reanalysis.
Actual piping accelerations as well as any additional valve support bracing were not included in this portion of the review because the results of this DCP reanalysis are to be used as~ criteria for the pip-ing system qualification.
No E0Is have been issued in this review area to date.
The verification program intended to be conducted by the IDVP is not yet complete. Based upon the efforts performed to August 15, 1983, I the IDVP considers the following aspects of the DCP work to be accept-able and to satisfy the licensing criteria.
e The methods and results of the reanalysis comply with the established DCP criteria.
e Mathematical modeling of the valve adequately represents the structure of the valve, e Critical areas were examined.
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IDVP 4.6.3-4 REV1 FINAL 830818
i St' F W NE ENGINEERING SERVICES O The IDVP considers the following aspects of the DCP work to be unre-solved concerns at this time.
e Resolution of the appropriate allowable stress criteria applicable to valve bolting.
The IDVP intends to formulate a final conclusiori as to the qualifica-tion of and its conformance to licensing criteria when the IDVP veri-fication is complete.
.(To Be Supplemented)
O O
IDVP 4.6.3-5 REV 1 FINAL 830818
"RTELEDYNE ENGINEERNG SERVICES o
V 4.6.4.3 Verification of DCP Activities The IOVP verification of DCP activities for Pumps is defined by ITRs
-8 and -35. The IOVP review examines the DCP work for all aspects described in Section 4.6.1 above. The results of this verification have been reported in ITR-67. l The DCP Internal Technical Program for Equipment consisted of a review of the seismic qualification. This review consisted of checking the latest seismic qualification data against those used for the qualifi-cation of equipment. This checking was performed using the latest response spectra for the DE, 00E, and Hosgri event. Whenever changes to the response spectra required requalification of the equipment, the equipment was requalified by analysis or testing. Equipment identi-fied for review consisted of those associated with the engineering safety systems designed by PGandE (Reference DCP Phase I Final q Report).
U Two identical fire pumps located in the Unit I Auxiliary Building at elevation 115 feet were selected as the IOVP verification sample. The fire pumps are Design Class I equipment.
This pump is one of eight pumps reviewed by the DCP. Of these eight, one was qualified by shake table testing (see Section 4.9.1) and is thus excluded from the' sampling of reviewed / reanalyzed pumps. Five of the remaining seven pumps were included in the IOVP initial sample and additonal verification work. Thus, with the IOVP review of the fire pump, six of the seven pumps qualified by analysis and in the IOVP scope have been verified.
The IOVP verification included assessments of the completeness, applicability, consistency, and adequacy of the OCP review and reanalysis methodology. Where discrepancies were noted, or
, methodology deemed not totally appropriate, alternate calculations V
IOVP 4.6.4.3-1 REV1 FINAL 830818
W TF1rtWNE ENGNEERING SERVICES C) were cerried out by the 10ve to verify the conciusioas of the DCe re-analysis.
E01 1140 was issued in connection with the fire pump and identified two concerns regarding the discharge nozzle flanged joint. ihe first concern, relative to bolt stresses was resolved as a closed item after further evaluation. The second concern, which involved a non-conformance of the installed flange configuration with PGandE piping specifications, resulted in an Error Class C.
The verification program intended to be conducted by the IOVP is not yet complete. Based upon the efforts performed to August 15, 1983, l the IOVP considers the following aspects of the DCP work to be acceptable:
e Operability, as defined by rotating element clearances and interfereces, was adequately demonstrated.
(3 LJ e The seismic spectra utilized by the DCP for pumps reflects the current spectra, e The mathematical modeling used in the reanalysis was judged to be acceptable for the fire pump.
e With the exception of the item identified in the next paragraph all established DCP criteria are judged to have been adequately met.
The IOVP considers the following aspects of the DCP work to be unre-solved concerns at this time.
e Flanges on pumps require reevaluation relating to the ap-propriate allowable stress values to be used for .the cast iron fire pump.
(o.i IOVP 4.6.4.3-2 REV1 FINAL 830818 l
4%9I WW ENGINEERING SERVICES Q The IOVP intends to formulate a final conclusion as to the qualifica-tion of pumps and their conformance to licensing criteria when the IDVP verification has been completed.
(To be supplemented)
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v IOVP 4.6.4.3-3 REV 0 FINAL 830818
WTF 1 MWNE ENGINEERING SERVICES O 4.6.5.2 Verification of DCP Activities
'he IDVP verification of DCP activities for heat exchangers is defined by ITRs -8 and -35. The IDVP verification of the DCP work includes all aspects ' described in Section 4.6.1. The results of the verifica-tion have been reported in ITR-67.
The DCP Internal Techn.ical Program for equipment consisted of a review of the seismic qualification. This review comprised checking the latest seismic qualification data against those used for the qualifi-cation of equipment. This checking was performed using the latest response spectra for the DE, DDE, and Hosgri event. Whenev w changes to the response spectra required requalification.of the equipment, the equipment was requalified by analysis or testing. Equipment identi-fied for review comprised that associated with the engineered safety systems designed by PGandE (Reference PGandE Phase I Final Report). ,
O The DCP performed a reanalysis of the CCW pump lube oil cooler with revised seismic imputs.
The CCW pump lube oil cooler was selected as the IDVP verification sample of the DCP's ITP activities for heat exchangers. One lube oil cooler is mounted with each of the three CCW pumps located in the aux-iliary building at elevation 73 feet. The CCW pump lube oil coolers are Design Class I Equipment. This cooler, or heat exchanger, is one of two heat exchangers reviewed by the DCP. The other was the CCW heat exchanger, which was in the IDVP initial sample.
The IDVP performed a design review of the reanalysis. A checklist was developed which covered all criteria items, and critical analytical procedures, and ensured completeness of the DCP review. In addition to the checklist, the IDVP work included assessments of the complete-ness, applicability, consistency of the reanalysis methodology. Where discrepancies were noted, or methodology was deemed not totally appro-p)
IDVP 4.6.5.2-1 REV 1 FINAL 830816
W TnPTWNE ENGINEERING SERVICES
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() priate, alternate calculations were carried out by the IOVP to verify the conclusions of the DCP reanalysis.
'One E01 file,1130, was established. The OCP reanalysis of the CCW pump lube oil cooler showed that allowable criteria were exceeded and that physical modifications were required. This reanalysis was the analysis of record when the OCP had indicated that all ITP work in this area was complete and no physical modifications were nec3ssary (DCP Phase I Final Report, Revision 3, dated 4/22/83). There is no concern with the engineering of this item. The IOVP determined that the status of qualification was internally tracked within the OCP and required actions would have been implemented, even though this was not apparent from the DCP Phase I Final Report. E0I 1130 was resolved as a Deviation.
The technical effort of the verification program incended to be con-ducted by the IOVP is complete except for IOVP/DCP agreement on the O
(j allowable stress criteria to be used for cast iron. Based upon the efforts performed to August 19, 1983, the IOVP considers the following aspects of the OCP work to be acceptable:
e Seismic spectra utilized in the reanalysis were the cur-rent spectra.
e .The methods and results of the reanalysis reviewed comply with the established DCP criteria.
e Mathematical modeling of the tank adequately represented the cooler structure.
e Because all DCP reviewed heat exchangers are included in the IOVP, all such heat exchangers have been verified as complying with criteria.
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IOVP 4.6.5.2-2 REV1 FINAL 830818
. . 1
1%' m W NE ENGINEERING SERVICES (3 -these other areas are sufficiently large, and they have LJ not identified any similar concerns (see other equipment sections).
e If there are further instances of incorrect bolt size, the IDVP does not believe there will be an impact on licensing criteria, for two reasons. First, the DCP has inspected '
all bolt sizes in HVAC equipment; any errors will be within measurement tolerances. Second, all discrepancies identified by the IDVP were small and did not affect I cr.iteria.
To further strengthen these conclusions, the IDVP performed further field verification for bolt sizes as part of the verification of ,
corrective action. The results of this field verification confirm the conclusions above.
O l
l IDVP 4.6.6.2-2 REV 1 FINAL 830818
WT51 ITVNE ENGNEERNG SERVICES n
U 4.6.6.3 Verification of DCP Activities - HVAC Equipment The IDVP performed verification of DCP activities for HVAC equipment in accordance with ITRs -8 and -35. The IDVP verification of the DCP work included all aspects described in Section 4.6.1 above. The samples selected for IDVP review are representative of Design Class I rotating machinery. The results of this verification have been presented in ITR-67. I The DCP Internal Technical Program (ITP) for equipment consisted of a review of the newest seismic qualification data against data used for the qualification of equipment. This check was performed using the latest response spectra for the DE, DDE and Hosgri event. Whenever changes to the response spectra required requalification of the equip-ment, this was done by analysis or testing. Equipment identified for review was that associated with the engineered safety systems designed by PGandE (see PGandE Phase 1 Final Report). *
]
The DCP assembled documentation packages for seismic qualification of all safety-related HVAC equipment. This equipment is identified and the method of seismic qualification is documented. The qualification is reviewed for effect of any seismic spectra changes. A reanalysis or test was performed if the spectra affected the qualification of the component. Redesign and modifications were implemented, if required, to maintain qualification.
i The sample selected by the IDVP for verification of the DCP'.s ITP for HVAC equipment consisted of supply fan S-1 and compressor CP-35.
Supply fan S-1 and an identical fan, S-2, are located in the auxiliary building at elevation 85 feet. Compressor CP-35 and an identical unit, CP-36, are located in the auxiliary building at elevation 154 feet, 6 inches. Both the fan and compressor are Design' Class I equip-ment.
O IDVP 4.6.6.3-1 REV1 FINAL 830816
W F W NE ENGINEERING SERVICES C) or incorrect value produced stresses within allowables. E0I 1125 was classified as a Class C Error. The resolution is discussed under "Hosgri Spectra," section 4.3.2.2.
E01 1127 was issued for two concerns over the modeling technique and methods used in the reanalysis of fan S-1. One concern was resolved as not significant based on the IOVP initial sample work. Th'e IOVP determined that the second concern was not valid and the OCP modeling method was correct. E01 1127 was classified as a Closed Item.
The technical aspects of the verification program conducted by the IDVP has been completed and reported in ITR-67. Based upon these efforts, the IOVP considers the following aspects of the OCP work to be acceptable and to satisfy the licensing criteria.
e The mathematical modeling of the structures was found to be adequate.
k.
e Application and satisfaction of established DCP criteria were found to be adequate.
e . A concern did exist over the proper control and applica-tion of seismic spectra, an issue which is related to work done in the initial sample. The concern was resolved as discussed in section 4.3.2.2.
The IOVP intends to formulate af ' inal conclusion as to the qualifica-tion of and its conformance to licensing criteria when the IOVP verif-ication is complete. The IOVP effort will include a completion sample to evaluate any changes in design input. l (ToBeSupplemented)
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v IOVP 4.6.6.3-3 REV 1 FINAL 830818
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'RTn m(NE ENGNEERING SERVICES i ) 4.6.7.3 Verification of DCP Activities The IDVP performed verification of DCP activities for electrical equipment in accordance with ITRs -8 and -35. The IDVP review exam-ined the DCP work for all aspects discussed in Section 4.6.1. This category of electrical equipment and instrumentation includes all such equipment qualified by analysis. This verification effort has been l reported in ITR-67. Equipment items qualified by shake table testing are discussed in Section 4.9.1.
The DCP reviewed the previous seismic qualifications of equipment to determine their validity with respect to current spectra for the DE, DDE, and Hosgri event. If the acalysis was invalid, the equipment was reanalyzed to ensure qualification to the current response spectra and then redesigned or modified as required. Equipment identified for review is equipment associated with the engineered safety systems designed by PGandE (see PGandE Phase I Final Report).
The station battery racks were selected as the IDVP verification sample of the DCP's review of electrical equipment qualified by anal-ysis. The racks support the station batteries, which are Design Class I equipment. This equipment is located in th.e auxiliary building at elevation 115 feet.
The station battery racks are one of five major items of electrical and instrumentation equipment qualified by analysis - that are within the IDVP scope. Major equipment in this case excludes small panels, transmitters, switches, circuit breakers and other small items of this type.
Of the five major equipment items, two were included in the IDVP ini-tial sample work: the main annunciator cabinet and the hot shutdown remote panel. Two others were included in the additional verification sample: the local instrument panels and the instrument AC panel.
(3 U
IDVP 4.6.7-3 REV1 FINAL 830816
l I
W Tpt m(NE ENGNEERING SERVICES O'
Thus, with the inclusion of the station battery racks, all analyzed major electrical equipment and instrumentation items have been included in the IDVP verification effort.
The IDVP performed a design review of the reanalysis performed by the DCP on the station battery racks, using a checklist to cover analysis criteria items, critical analytical procedures, and completeness of the DCP review, In addition to the checklist, the IDVP design review included assessments on the completeness, applicability, consistency and adequacy of the DCP review and reanalysis methodology. Where discrepancies were noted, alternate calculations were carried out by the IDVP to verify the conclusions of the DCP reanalysis.
Results of the IDVP reviews of the DCP reanalysis of the station battery racks are:
O e Seismic spectra used in the reanalysis were the current U
spectra.
e No specific analysis criteria were formally established for this equipment. However, the American Institute of Steel Construction Code was used by the DCP as criteria for the structural analysis, e An incorrect bolt size was used in the analysis.
(See E01 1128).
E01 1128 notes that in the DCP reanalysis of the station battery racks 3/8 inch bolts were used instead of the 1/2 inch bolts called for and the shear force was incorrectly calculated. A further IDVP evaluation indicated that the structural integrity of the racks was not impaired.
E01 1128 was resolved as an Error Class C.
p
%s IDVP 4.6.7-4 FINAL REV1 830818 1
1 1
'R TELED(NE ENGINEERINGSERVICES i
The verification program intended to be conducted by the IDVP is com-g plete. The IDVP considers the following aspe'ts c of the DCP work to be I acceptable and to satisfy the licensing criteria.
e The seismic response spectra used by the DCP for elec-trical equipment and instrumentation qualified by analysis reflects the current spectra.
I e Although no spec'ific criteria have been established by the DCP for analyses in this area, use of the AISC C' ode is adequate.
o The mathematical modeling used for. the reanalysis was con-sidered to be acceptable and the results of the reanalysi's -
comply with DCP criteria.
The IDVP intends to formulate a final conclusion as to the qualifi- '
(x~NJ cation of all electrical equipment and instrumentation and its con-formance to licensing criteria when all.IDVP verification work in this area is complete. Effects of any changes in the seismic design inputs will be evaluated as part of the IDVP Completion Sample.
(To Be Supplemented) v)
IDVP 4.6.7-5 P,EV 1 FINAL 830818
__ ____ _ _--_ ________-- - _A
F - .
" 1%V I W NE ENGNEERNG SERVICES
[]) \ The- procedure utilized by thc' IOVP to perform the design
, ' reviews involved a' combination of design review checklists and alternate calculations. The latter were performeo in those cases where checklist review results were not suffi-cient' to verify that supports rret licensing commitments.
The IOVP verification of the DCP plan implementation was based on a .100 percent sample of the OCP program for in-strument tubing and supports. The OCP program implementa-tion is contained in sir. qualification analysis packages which make up the IDVP scope for design review. One of
_ the six packages contains -the generic tubing span qualifi-s cations. The ramaining five contain tubing support quali-fications based on a DCP walkdown to identify controlling or specific wucst-case configurations within the contain-ment ahnulus. ,'
O E01 1123 was issued due to .the use of incorrect member properties for a particular support type. The member properties were different from both the OCP documented as-built information and the IOVP field verified data, which were equivalent. The DCP concurred with this assessment of the discrepancy, and the file was classified as a Class C Error.
The verification program intended to be conducted by the IOVP is not yet complete. Based upon the efforts per-formed to June 25,1983, the 10VP considers the following aspects of the DCP work to be acceptable:
e' Four DCP qualification analyses have been verified to be in conformance with procedures.
m
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IOVP 4.6.8.2-3 REV1 {
FINAL 830818 a h .n
i WTF1 FrWNE ENGINEERING SERVICES O . .
The oce nrovioed sufficient ead eccurete es-suiit-survey docu;nentation supporting DCP qualification an-alyses for 12 support types.
The IOVP intends t'o' formulate a final conclusion as to the I
qualification of instrument tubing and supports and their conformance to licensing criteria wnen the IDVP verifica-tion has been completed.
l (To Be Supplemented)
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IDVP 4.6.8.2-4 l FINAL REV 1 i 830818 l
TF WE ENGNEERNG SElWICES (3
g 4.6.9 Filters The IDVP verification of DCP activities for filters is defined by ITRs-8 and -35'. The IDVP verification of the DCP work included all aspects described in 4.6.1. The results of the verification have been l reported in ITR-67.
The DCP Internal Technical Program for filters involved a review of the seismic qualification. This review consisted of checking the newest seismic qualification data against data used for the qualifi-cation of equipment. This check was performed using the latest res-ponse spectra for the DE, DDE, and Hosgri event. Whenever changes to the response spectra required requalification of the eqitipment, the equipment was requalified by analysis or testing. Equipment identi-fied for review comprised that associated with the engineered safety j systems designed by PGandE (Reference PGandE Phase I Final Report).
this includes the safety injection pump lube oil filter, diesel oil
(]
transfer filter, and the strainer.
The safety injection pump lube oil filter was selected as the IDVP verification sample. One lube oil filter is mounted with each of the two safety injection pumps located in,the auxiliary building at eleva-tion 85 feet. The safety injection pump lube oil coolers are Design Class I equipment.
For the safety injection lube oil filter, the IDVP performed a design review of the the DCP reanalysis. A design review checklist was developed which covered all criteria items, critical analytical proce-dures, and completeness of the DCP review. In addition to the check-
, list, the IDVP. design review included reviewer assessments on the com-pleteness, applicability, consistency, and reanalysis methodology.
Where discrepancies were noted, or methodology deemed not totally v
IDVP 4.6.9-1 REV1 FINAL 830816
TE WE ENGNEERING SERVICES O eparopriate, aiternate ceicuiations were carried out 81 the 10ve to verify the conclusions of the OCP reanalysis.
No E01 files were established for this category of equipment.
The technical aspects of the vsification program conducted by the 10VP' has been completed and reported in ITR-67. Based upon these l
efforts, the IOVP considers the following aspects of the OCP work to be acceptable and to satisfy the licensing criteria:
e The seismic spectra utilized by the OCP for the filter reflect the current spectra (see 7.0).
e Mathematical modeling adequately represented the filter and support structure.
e The methods and results of the reanalysis comply with O estesiished DCe criterie.
The IOVP intends to formulate a final conclusion as to the qualifi-cation of all mechanical equipment and its conformance to licensing criteria when all IOVP verification work in this area is complete.
Effects of future revisions to the seismic inputs on equipment will be evaluated as part of the IOVP Completion Sample. I (To Be Supplemented)
(O IOVP 4.6.9-2 REV 1 FINAL 830818
l "RTF1 FrVNE ENGNEERNG SERVICES
~
In addition, utilizing the DCP jet impingement review results for a sample of high-energy lines, the IDVP verified the jet-target interactions of each sampled postulated line break, and reviewed the safety effects on safety-related equipment.
~
High energy lines were selected by the IDVP to represent approximately 10 percent of the estimated total number of postulated HELBs inside containment. The sample consisted of large and small lines including reactor coolant piping as well as secondary system piping. Since the IDVP verification was conducted prior to the completion by the DCP of their reanalysis effort, the IDVP sample was drawn from the completed work available. This represented approximately 50 percent of the high erergy lines inside containment. The IDVP field verified the jet-target interactions of each sampled postulated line break and reviewed the DCP safety evaluation of the effects of these jet-target interactions.
p As a result of the IDVP verification, four items of possible concern ere identified and are reported in E01 8065. The DCP failed to properly identify these four safety-related targets which were l impinged upon by the sampled postulated pipe break events. However, in comparison to the total of 273 DCP-identified jet-target interactions determined adequate by the IDVP, it was concluded that these four discrepancies were isolated instances and were not indicative of any generic deficiency in the jet impingement field review. In addition, the results of further evaluation of these jet-target interactions indicated that accident mitigation capabilities would not be impaired due to these localized jet impingement effects. On this basis, E01 File 8065 was closed.
The DCP reanalysis program as established by the procedure and criteria as well as the sampled documentation of this jet impingement reanalysis provided sufficient information for the IDVP to conclude that the specific concerns in E0I File 7002 were adequately addressed cx and documented. E01 File 7002 was closed.
'd' IDVP 4.8.5-2 REV 1 FINAL 830816
10TELEDYNE ENGINEERING SEFNICES o
O where the number used is that for the E01 File identified as a Find-ing. A history of each E01 File is contained in the LISTLOG printout in Appendix 0. The ITRs which include a detailed presentation of the subject are identified in Table 5-1 and additional information is available from the cross-indexes in Appendix E. Table 5-1 also refer-ences the final report section, or sections, which summarize the tech-nical aspects of the file.
Although each E01 File identified as a Finding has been classified by the IDVP as an ER/A, ER/AB, or ER'/B, there are three different bases for that classification, specifically:
e 13 files (932, 938, 949, 963, 983, 1069, 8001, 8009, 8010, 8012, 8017, 8057, 8062) were classified on the basis of a l
technical error identified during verification of the initial sample.
O e 1 fiie (7002) was ciessified on the basis of the love evaluation of the QA Audits and Reviews.
e- 7 files (1003, 1014, 1022, 1026, 1092, 1097, 1098) were classified as a result of the establishment of the DCP Corrective Action Program.
With respect to the last basis, none of these seven E0I Files had been fully resolved by the IDVP at the time the Corrective Action Program (CAP) was established. When the CAP was established, each of these files was ro. defined to track the generic DCP action and was resolved by verification of DCP activities in accordance with ITR-8 and -35.
E01 File 7002 also led to generic DCP action which was verified in accordance with ITR-34.
With respect to the 13 E01 Files which resulted in a Finding on the basis of a technical error, 6 developed from RLCA Phase I work and 7
,, from SWEC Phase II work. Of the 6 RLCA originated files, one (983)
V IDVP 5.2-2 REV 2 FINAL 830805
W P W NE ENGINEERNG SERVCES (q) was redefined to cover generic CAP efforts. The remaining 5 files l were concerns specific to the item being evaluated by RCLA, but all were influential in defining expanded IDVP activities in ITRs-1 or -8.
l All 7 SWEC originated files were specific concerns, and all 7 con-l tributed to the identification of four generic concerns which were verified in accordance with ITR-34.
Several of the Table 5-1 pages indicate that other E01 Files were com-bine'd with the file identified as the Finding. The existence of such combined files should not be interpreted as increasing or decreasing l the number of Findings. In no case were two or more Findings combin-ed. In all cases, each of the files being combined was tracking a common concern. By combining the files, the overall concern was more readily tracked and each was more certain of proper resolution. When the combination was with an E01 File originated by RCLA, the combined concern was being addressed as part of the CAP and was subject to IDVP
{} verification in accordance with ITRs-8 and -35. There were only two cases (E018001s and 8012) where SWEC originated files were combined; one also included two RFR originated files. The former affected the evaluation of environmental conditions outside of containment and were resolved by DCP activities verified in accordance with ITR-34. E0I 8012 considered separation and single failure criteria of Class 1E CRVP power supplies.
O v
IDVP 5.2-3 REV 2 FINAL 830805
"A P W NE ENGNEERNG SERVICES n
v TABLE 5-1-1003 SIGNIFICANT FINDING: E01 FILE: 1003 PHYSICALMODIFICATION(S)?: No ERROR CLASS: A/B l TITLE: HVAC Duct Support Reanalyses
- 1. THE FOLLOWING E0I FILE NUMBERS WERE COMBINED WITH THIS FILE: LL77
- 3. SU M ARY OF CONCERN:
Certain HVAC duct supports may not have been evaluated for Hosgri loadings prior to 811008.
O 4. SumaRv 0F ReS0tuTION:
DCP comitted to review the seismic analysis and -design 'of all Design Class 1 HVAC duct supports per Rev. O to Section 2.5.1 of the DCP Phase I Final Report and to reanalyze and, if necessary, redesign such supports.
The IDVP has verified the DCP Corrective Action per ITRs-8 and -35, with the exception of the concern addressed by E01 1134 (having to do with the application of the Rayleigh-Ritz method) which will be separately addressed.
- 6. FOR FURTHER INFORMATION SEE:
APPENDIX D AND SUBSECTION (S): 4.6.6 INTERIM TECHNICAL REPORT (S): 15 and 63 O
IDVP REV 2 FINAL 830816 i
"MTri mVNE ENGNEERING SERVICES O TABLE 5-1-1022 SIGNIFICANT FINDING: E01 FILE: 1022 PHYSICALMODIFICATION(S)?: No ERROR CLASS: A/B l TITLE: Intake Structure Reevaluation
- 1. THE FOLLOWING E01 FILE NUMBERS WERE COMBINED WITH THIS FILE: 967 and i 988
- 2. STRUCTURE (S), SYSTEM (S) OR COMPONENT (S) INVOLVED: Intake structure
- 3. SlDMARi 0F CONCERN:
As a result of IDVP concerns listed in the above files and their own internal technical program review, the DCP committed to a reevaluation of the Intake Structure in their corrective action program.
O Modifications made with respect to wave-force effects must be considered in the seismic reevaluation.
l 4. SlDMARY OF RESOLUTION:
Verification of DCP Corrective Action is complete.
l l
- 6. FOR FURTHER INFORMATION SEE:
APPENDIX 0 AND SUBSECTION (S): 4.3 and 4.4.6 O INTERIM TECHNICAL REPORT (S): 10, 32, and 58 IDVP REV 2 FINAL 830816
4% W % NE ENGNEERING SBWICES l TABLE 5-1-1069 SIGNIFICANT FINDING: E01 FILE: 1069 PHYSICALMODIFICATION(S)?: Yes ERROR CLASS: A f TITLE: Auxiliary Feedwater System Valves LCV-113 and LCV-115
- 1. THE FOLLOWING E0I FILE NUMBERS WERE COMBINED WITH THIS FILE: None
- 2. STRUCTURE (S), SYSTEM (S) OR COMPONENT (S) INVOLVED: Valves LCV-113 and LCV-115
- 3. StM4ARY OF CONCERN:
PGandE Piping Design Analysis 2-14 (prior to 811130) indicated that supports are not required on the valves. The RLCA verification analysis showed supports are needed. This fact was confirmed with a later PGandE analysis. Also, PGandE to obtain approval from the valve supplier of the addition of supports on tiie valve operator.
- 4. SIM4ARY OF RESOLUTION:
Verification of modification and of valve qualification with the added supports is complete.
S. RESULTED IN ADDITIONAL VERIFICATION / SAMPLE OR VERIFICATION OF DCP EFFORTS PER ITR(S): 8
- 6. FOR FURTHER INFORMATION SEE: ;
APPENDIX D AND SUBSECTION (S): 4.5.2 INTERIMTECHNICALREPORT(S): 12 and 59 IOVP REV 1 FINAL 830816
'RTF157WNE ENGINEERING SERVICES TABLE 5-1-1092 SIGNIFICANT FINDING: E0I FILE: 1092 PHYSICALMODIFICATION(S)?: Yes ERROR CLASS: A TITLE: Fuel Handling Building Reevaluation
- 1. THE FOLLOWING E0I FILE NUMBERS WERE COMBINED WITH THIS FILE: 990, 991, 1027, 1079, and 1091 l
- 2. STRUCTURE (S), SYSTEM (S) OR COMPONENT (S) INVOLVED: Fuel Handling Building
- 3. SUPMARY OF CONCERN:
As a result of IDVP concerns listed in the above files and their own internal technical review, the DCP committed to a reevaluation of
.the Fuel Handling Building in this corrective action program.
O
- 4. SUPMARY OF RESOLUTION:
Verificat' ion of DCP Corrective Action is complete except for field verification against the design drawings used as the basis for the analyses.
- 6. FOR FURTHER INFORMATION SEE:
APPENDIX D AND SUBSECTION (S): 4.4.3 INTERIMTECHNICALREPORT(S): 6 and 57 IDVP REV 2 FINAL 830816
1%VI WNE ENGNEERNG SERVCES O Tas'c s-2-1224 SIGNIFICANT FINDING: E0I FILE: 1124 PHYSICALMODIFICATION(S)?: NO ERROR CLASS: B TITLE: Auxiliary Building Spectra Generation
- 1. THE FOLLOWING E0I FILE NtMBERS WERE COMBINED WITH THIS FILE: None l
- 2. STRUCTURE (S), SYSTEM (S) OR COMPONENT (S) INVOLVED:
Control Room Floor Slab
- 3. St# MARY OF CONCERN:
The design analysis finite element model of the control room slab used to generate Hosgri response spectra did not agree with the l field verified location of the supporting walls.
The DCP has revised the finite element model to agree with the field verified dimensions. At certain frequencies the response spectra have increased by more than 15 percent.
( 4. SUDMARY OF RESOLUTION:
1 I Resolved through IDVP verification of the revised DCP analysis. l
- 6. FOR FURTHER INFORMATION SEE:
APPENDIXDANDSUBSECTION(S): 4.4.2 INTERINTECHNICALREPORT(S): 55 O
IDVP REV 1 FINAL 830816
l l
SPTF1 PTVNE ENGdNEERING SEFMCES O TABLE 5-3-1069 MODIFICATION IN RESPONSE TO SPECIFIC ERROR: E01 FILE: 1069 ERROR CLASS: A c
- 1. STRUCTURE (S), SYSTEM (S), OR COMPONENT (S) INVOLVED:
Auxiliary Feedwater System, Analysis 2-14
\
- 2. DESCRIPTION OF PHYSICAL MODIFICATION:
Addition of supports on valves LCV 113 and LCV 115.
- 3. PHYSICAL MODIFICATION VERIFIED BY IDVP: Yes !
- 4. FURTHER DESCRIPTION IS AVAILABLE IN TABLE 5-1-1069 AND IN PGandE PHASE I FINAL REPORT:
SECTION(S): 1.7.2; Appendix 1C TABLE (S): 2.2.1-4 O
IDVP REV 1 FINAL 830816
I l
WTA WNE ENGINEERING SERVCES
(-
6.4.3 Significance as Indicated by E01 File Classification The E01 File classification system described in 3.6.2 included a clas-sification method. As described in Section 5, the most significant errors, which were termed Findings, were identified by classification as Class A, Class A or Class B, or Class B Errors with no intent to distinguish significance among such classes. All IDVP Findings are summarized in Tables 5-1 and 5-2. As is indicated by the table in-cluded in 5.5.4, 8 percent of the initial sample and additional veri-l fication/ sample E0I Files were classified as Findings. Another 16 percent of these Files were combined with Findings as discussed in Section 5.
The second most significant grouping was that termed Observations, which included all E01 Files classified as Class C Errors or as Devia-tions. This category would have also included Class D Errors had any been identified. E01 Files classified as Observations are summarized
(]' by 5.5, and included 38 percent of the initial sample and additional verification / sample files.
The remaining E01 Files resulting from the initial sample and addi-tional verification / sample efforts were classed as being neither Find-ings or Errors. These were 37 percent of the total.
Several of the E01 Files resulted in the ;:erformance of modifications.
The performance of modifications is a measure of significance, in that the absence of modifications would indicate a negligible impact of the IDVP on the a:tual DCNPP-1 configuration and imply that any errors identified by the IDVP were only " paper" concerns. The matter of mod-ifications is treated briefly in 6.5, which references back to 5.4 -
and, specifically, to Tables 5-3 and 5-4.
()
v IDVP 6.4.3-1 REV 1 FINAL 830805
WF mVNE ENGINEERING SERVCES O 7.4 Iove status as 0F auNE 25, 1983 This report was based upon the IDVP status as of June 25, 1983 and the last revision considers additional work through August 19, 1983. The 3 overall status may be summarized by the statement that the IDVP has completed all Phase I and Phase II efforts in accordance with the NRC-approved plans with the following exceptions:
e RLCA soils efforts defined by ITR-1 and subsequently ex-panded by staff comment e Certain RLCA efforts defined by ITRs-8 and -35 The RLCA efforts are to be completed by supplementing various subsec-1 tions of this report and by the issuance of various ITRs.
, Table 7.4-1 summarizes the status of the IOVP effort as of August 19, l kJ 1983. The first column identifies all portions of this IOVP Final Report which must be supplemented at a later date to report completion of the IDVP effort defined by ITRs-8 and -35. The second column l provides a cross-reference to the PGandE Final Report sections which report on the same subject, and is also useful in examining the DCP status which is indexed in Table 7.3-1 through 7.3-6 by these ncmbers.
The third column of Table 7.4-1 identifies those E0I Files which per-tain to each of the incomplete subsection; ar.d which were unresolved as of August 19 1983.
l j
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IDVP 7.4-1 REV1 FINAL 830818 1
WTF1 FrT(NE ENGNEERING SERVICES i
{} The fourth column of Table 7.4-1 identifies the ITR which will be
. issued to report the details of the IDVP work summarized in the listed IOVP Final Report subsection, as well as the future efforts required to complete the 10VP. These include ITRs-51, 56, -59, -60, -61, i
-63, -65, and -68. All other ITRs have been issued, except that ITRs-52 and -53 have been replaced by ITR-68, ITR-62 will be combined with ITR-60, and ITRs-64 and -66 will be combined with ITR-63.
The last three columns of Table 7.4-1 summarize the status of IOVP verification. In all cases, the IOVP verification program is that contained in either ITR-8 or -35. The column headings are: l e " Field" - indicates the status of field verification, not including field verification of modifications.
e " Design" - indicates the status of verification of DCP de-sign efforts.
O e " Mod" - indicates the status of IDVP field verification of physical modifications.
One of four terms (Yes, Part, No or NA) is entered in Table 7.4-1 to sumarize the IOVP status.
e In the first of these last three columns: "Yes" means that the 10VP has completed this field verification; "No" means thct IDVP field verification is planned, but not yet completed; and, " iia" means that field verification is not applicable.
e In the second of these last three columns: "Yes" means that the IDVP has completed their design verification I effort except, where applicable, the field verification of modifications; "Part" means that the IOVP has completed a
/~)N
'w IDVP 7.4-2 REV 1 FINAL 830818
l
'RTELEDYNE ENGNEERING SERVICES TABLE 7.4-1 f]
STATUS OF INCOMPLETE VERIFICATIONS DEFINED BY ITRS-8, -34, AND -35 Report Subsections Verification Complete?
Unresolved ITR IOVP PGandE E0Is No. Field Design Mod 4.4.2.2 2.1.2 1097 55 Yes No NA 4.4.3 2.1.3 1092 57-1 NA Yes No u 4.4.4 2.1.1 1014 54 NA No No 4.4.5 2.1.1.4.3 1014 51 Yes No No 4.4.6 2.1.5 58-1 Yes Yes NA 4.4.8 2.1.4 1026 56 Yes No No 1028 4.5.2.3a 2.2.1 938 59 Yes Part No 1098 1138 1141 4.5.2.3b 2.2.3 1098 60 Yes Part No l 4.5.3.2a 2.2.2 1098 61 Yes Part NA 1141 4.5.3.2b 2.2.2 1098 60 Yes Part No 114P 4.6.2.2 2.3.1 67-1 NA Yes NA 4.6.3 2.3.1 67-1 NA Part NA 4.6.4 2,3.1 67-1 Yes Part NA 4.6.5 2.-3.1 67-1 Yes Part NA 4.6.6.3 2.3.3 67-1 Yes Yes NA 4.6.6.5 2.5 1134 63 No Part No IOVP REV1 FINAL 1 of 2 830816
. . - . . - -_ _ _ _ _ _ ______---_-_-_-------_-_---__-------_--_--_--u
"#PTpt FrWNE ENGNEERING SERVICES O TABLE 7.4-1 (Coat)
Report Subsections Verification Complete?
Unresolved ITR IDVP PGandE E0Is No. Field Design Mod 4.6.7 2.3.2 67-1 Yes Yes NA 4.6.8.lb 2.4 983 63 ies Yes No 4.6.8.2b 2.6 63 fes Yes NA l 4.6.9 NA NA 67-1 Yes Yes NA I
4.9.1.4 2.3.2.3.3 NA 67-1 NA Yes NA 4.9.2 NA NA 68 Yes No NA 4.9.3 NA NA 65 N6 No No O
I 1
IOVP REV 1 l FINAL 2 of 2 830816
!}
SECTION
8.0 REFERENCES
8.1 IOVP DOCUMENTATION 8.1.1 Teledyne Engineering Services The following~ ITRs and Program Plans have been published by Teledyne Engineering Services, 130 Second Avenue, Waltham, Massachusetts.
e Diablo Canyon Nuclear Power Plant Design Verification Program Management Plan Phase I, March 29, 1982.
o Diablo Canyon Nuclear Power Plant Design Verification Program Management Plan Phase II, June 18, 1982.
e Diablo Canyon Nuclear Power Plant - Independent Design Verification Program Adjunct Program for . Evaluation of Construction Quality Assurance, November 1982.
e ITR-2: Coments on the R. F. Reedy, Inc., Quality Assurance Q Audit Report on Safety-Related Activities Performed by Pacific Gas and Electric Prior to June 1978.
Revision 0, June 23, 1982 e ITR-ll: Pacific Gas and Electric - Westinghouse Seismic Interface Review.
Revision 0, November 2, 1982 e ITR-50: Containment Annulus Structure Vertical Seismic Evaluation.
Revision 0, July 22, 1983 (a')
IDVP 8.1.1-1 REV 1 FINAL 830815
)
WM ENGNEERING SERVICES o
V e ITR-16: Soils - Outdoor Water Storage Tanks.
Revision 0, December 8, 1982 e ITR-17: Piping - Additional Sanples. ,
Revision 0, Decenber 14, 1982 l e ITR-30: Small Bore Piping Report.
Revision 0, January 12, 1983 e ITR-31: HVAC Components.
Revision 0, January 14, 1983 l Revision 1, August 4, 1983 e ITR-32: Pumps.
Revision 0, February 17, 1983 Revision 1, April 1, 1983 e ITR-33: Electrical Equipment Analysis.
Revision 0, February 18, 1983 Revision 1, April 28, 1983 e ITR-35: Independent Design Verification Program Verification Plan for Diablo Canyon Project Activities.
Revision 0, April 1, 1983 e ITR-37: Valves.
Revision 0, February 23, 1983 e ITR-39: Scils - Intake Structure Cearing Capacity and Lateral Earth Pr ssure.
Revision 0, February 25, 1983 e ITR-40: Soils Repo'-t - Intake Sliding Resistance.
Revision 0, March 9, 1983
- e. ITR-43: Heat Er. changers.
Revision 0, April 14, 1983 e ITR-44: Shake Table Test Mounting Class lE Electrical Equipment.
Revision 0, April 15, 1983 A
V 8.1.2-2 REV 1 830815
1%' F W NE ENGNEERNG SEFNICES o
O e ITR-57: Review of DCP Activities Fuel Handling Building.
Revision 0, August 1, 1983 e ITR-58: Verification of DCP Activities Intake Structure.
Revision 0, August 8, 1983 e ITR-67: Large and Small Bore Pipe Supports.
Revision 0, August 12, 1983 e Preliminary Report on the Design Interface Review of the Seismic Reverification Program, Novenber 12, 1981.
e Design Verification Program, Seismic Service-Related Contracts Prior to June 1978.
Revision 0, Decenber 3, 1981 Revision 1 February 27, 1982 e Design Verification Program for Power Ascension - Diablo Canyon Nuclear Power Plant - Unit 1.
Revision 0, January 9, 1982 O
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. . -3 NL REV 1 830815
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l WTF1 m(NE ENGNEERNG SEFMCES v
8.1.4 Stone & Webster Engineering Corporation The following ITRs and Program Plans have been published by Stone &
Webster Engineering Corporation, 245 Summer Street, Boston, Massachusetts, e ITR-14: Verification of the Pressure, Temperature, Humidity, and Submergence Environments Used for Safety-Related Equipment Specifications Outside Containment for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System.
Revision 0, December 6,1982 Revision 1, May 9, 1983 Revision 2, July 25, 1983 e ITR-18: Verification of the Fire Protection Provided -for Auxiliary Feedwater System, Control Room Ventilation and Pressurization System Safety-Related Portion of the 4160 V Electric System.
Revision.0, December 13, 1982 Revision 1, May 24, 1983 e ITR-19: Verification of the Post-LOCA Portion of the O
Radiation Environments Used for Safety-Related Equipment Specification Outside Containment for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System.
Revision 0, December 16, 1982 e ITR-20: Verification of the Mechanical / Nuclear Design of the Control Rcom Ventilation and Pressurization System.
Revision 0, December 16, 1982 Revision 1, April 20, 1983 Revision 2, July 25, 1983 e .ITR-21: Verificatitm of the Effects of High Energy Line Cracks and Moderate Energy Line Breaks for Auxiliary Feedwater System and Control Room Ventilation and f ressuruation System.
Revision 0, Decemoer 15, 1932 Revision 1, May 3, 1983 e ITR-22: Verification of the Mechanical / Nuclear Portion of the Auxiliary Feedwater System.
Revision 0, December 17, 1982 Revision 1, April 20, 1983 Revision 2, July 25, 1983 wJ IDVP 8.1.4-1 REV 1 FINAL 830815
4%9 % NE ENGNEERING SERVICES q
V e ITR-23: Verification of High Energy Line Break and Internally Generated Missile Review Outside Containment for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System.
Revision 0, Decenter 20, 1982 Revision 1, May 27, 1983 e ITR-24: Verification of the 4160 V Safety-Related Electrical Distribution System.
Revision 0, Decenter 21, 1982 Revision 1, May 4, 1983 e ITR-25: Verification of the Auxiliary Feedwater System Electrical Design.
Revision 0, December 21, 1982 l Revision 1, April 29, 1983 e ITR-26: Verification of the Control Room Ventilation and Pressurization System Electrical Design.
Revision 0, December 21, 1982 Revision 1, May 2, 1983 O
V e ITR-27: Verification of the Instrument and Control Design of the Auxiliary Feedwater System.
l Revision 0, December 23, 1982 l Revision 1, May 13, 1983 Revision 2, July 25, 1983 l e ITR-28: Verif nation of tce instrument and Ccntrol Design'of the Control Room Ventilation ar.d Pressurization System.
Revision 0, December 23, 1982 Revision 1, May 13, 1983 I Revision 2, July 25, 1983 l
e ITR-29: Design Chain - Initial Suple.
Revisien 0, January 17, 1983 e ITR-34: Verification of DCP Efforts by Stone & Webster Engineering Corporation.
Revision 0, February 4, 1983 Revision 1, March 24, 1983 e ITR-36: Final Report on Construction Quality Assurance Evaluation of G. F. Atkinson.
p v
Revision 0, February 25, 1983 Revision 1, June 20, 1983 IDVP 8.1.4-2 REV 1 FINAL 830815
WTA WNE ENGNEERING SERVICES o
V e ITR-38: Final Report on Construc tion Quality Assurance Evaluation of Wismer & Becker.
Revision 0, March 1, 1983 Revision 1, March 16, 1983 Revision 2, June 20, 1983 e ITR-45: Additional Verification of Redundancy of Equipment and Power Supplies in Shared Safety-Related Systems.
Revision 0, May 17, 1983 e ITR-46: Additional Verification of Selection of System Design -
Pressure and Temperature and Differential Pressure Across Power-0perated Valves.
Revision 0, June 27, 1983 s ITR-47: Additional Verification of Environmental Consequences of Postulated Pipe Ruptures Outside of Containment. l Revision 0, June 27, 1983 e ITR-48: Additional Verification of Jet Impingement Effects of
, O eastuleted eine Ruptures taside Coateiament- t Revision 0, July'27, 1983 l
e ITR-49: Additional Verification of Circuit Separation and l Single Failure Review of Safety-Related Electrical Equipment. J Revision 0, June 23, 1983 l
l l
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V 8.1.4-3 REV 1 830815
"W TF1FD(NE ENGINEERING SERVICES v
8.2 OPEN MEETINGS 8.2.1 NRC Meetings (Transcribed)
The following meetings were transcribed. The date of the meeting and the attendees are listed.
October 9, 1981, Nuclear Regulatory Comission and Pacific Gas and Electric Company.
February 3, 1982, Nuclear Regulatory Comission, Pacific Gas and Electric Company, Teledyne Engineering Services, Robert L. Cloud Associates, and Stone & Webster Engineering Corporation.
March 25, 1982, Nuclear Regulatory Comission, Pacific Gas and Electric l Company, Teledyne Engineering Services, Robert L. Cloud Associates, l Stone & Webster Engineering Corporation, and Roger F. Reedy, Inc. l April 1,1982, Nuclear Regulatory Comission, Pacific Gas and Electric
- Company, Teledyne Engineering Services, Robert L. Cloud Associates, Roger F. Reedy, Inc., and Stone & Webster Engineering Corporation.
June 10, 1982, Nuclear Regulatory Comission, Diablo Canyon Project,
(] Teledyne Engineering Services, Robert L. Cloud Associates, and Roger F.
v Reedy, Inc.
July 27, 1982, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, and
, Brookhaven National Laboratories.
1 August 6,1982, Nuclear Regulatory Comissica, Pacific Cas and Electric )
Company, Teledyne Engineering Services, Robert L. Cloud Asscciates, l Roger F. Reedy, Inc., Stone & Webster Engineering Corporation, and Designated Other Parties.
Septenter 1, 1982, Nuclear Regulatory Comission, Pacific Gas and Electric Ccmpany, Teledyne Engineering Services, Robert L. Cloud Associates, Roger F. Reedy, Inc., Stone & Webster Engineering Corpor; tion, Designe tec' Other Laboratories.
Parties, and Brookhaven National l October 19, 1982, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, and Stone &
Webster Engineering Corporation.
October 20, 1982. Nuclear Regulatory Comission.
g V
IDVP 8.2.1-1 REV 1 FINAL 830815
WTri pr?(NE ENGINEERING SERVICES (3
Noventer 10, 1982, Nuclear Regulatory Comission and Designated Other Parties.
December 8,1982, Nuclear Regulatory Comission.
Decenber 21, 1982 Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Brookhaven National Laboratories, and Westinghouse.
January 13, 1983, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, Roger F.
Reedy, Inc., and Designated Other Parties.
January 28, 1983, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Stone & Webster Engineering Corporation, and Westinghouse, lu February 15, 1983, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, Designated Other Parties,.and Brookhaven National Laboratories.
May -4,1983, Nuclear Regulatory Comission, Pacific Gas and Electric Company, Teledyne Engineering Services, and Designated Other Parties, n
L.) May 20, 1983, Nuclear Regulatory Comission, Teledyne Engineering Services, Stone & Webster Engineering Corporation, Designated Other Parties, and Westinghouse.
May 21, 1983, Nuclear Regulatory Comission, Teledyre Engineering Services, Store & Webster Engineering Corooraticn, Designated . 0ther g Parties, and Westir< shou,e. 5 June 17, 1983, Nucleer Regulatory Comnission, Robert L. Cloud Associates, Diablo Ca'iycn Project, Erookhaven Natior.a1 Laboratories and Designated 9ther Parties. :.
July 6, 1983, Nuclear Regulatory Cemission, Diablo Canycn Project, Teledyne Engineering Services, Brookhaven National Laboratories.
July 14, 1983, huclear Regulatory Ccmissica, Pacific Gas and Electric Company, and Designated Otner Parties.
Augu st 10, 1983, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, and Designated Other Parties.
\v' IDVP 8.2.1-2 REV 1 FINAL 830815
W F W NE ENGINEERNG SERVICES m
U 8.2.2 Other "Open" Meetings Noventer 12, 1982, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, and Brookhaven National Laboratories.
December 9, 1982, Nuclear Regulatory Comission, Pacific Gas and Electric Cowany, Teledyne Engineering Services, and Robert L. Cloud Associates, December 14-15, 1982, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, and Robert L. Cloud Associates.
December 20, 1982, Nuclear Regulatory Comdsion, Diablo Canyon Project, Teledyne Engineering Services, and Roger F. Reedy, Inc.
. February 4,1983, Nuclear Regulatory Comission Diablo Canyon Project, l Teledyne Engineering Services, Robert !.. Cloud Associates, Roger F.
Reedy, Inc., Stone & Webster Engineering Corporation, and Brookhaven l National Laboratories.
February 14, 1983, Nuclear Regulatory Comission and Brookhaven National i Laboratories.
1 (d )
April 21,1983, Nuclear Regulatory Commission, Diablo Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, Roger F.
Reedy, Inc., and Stone & Webster Engineering Corporation.
f l
April 25-26,1983, Nuclear Regulatory Comissien, (nablo Canyon Project, Teledyne Engineeri39 Services, Stone & Webster Engineering Corporation, and Designated Otner Partfes.
April 26-27, 1983, Nuclear Regulatory Comissior., Diablo Canyran Project.
Teledyne Engineering Services, and Robert L. Cloud Associates.
April 27-28, 1983, Nuclear Regulatory Comission, Diablo Canyon Project, Teledyne Engineering Services, and Robert L. Cloud Associates.
May 12, 1983, Nuclear Regulatory Comission, Diabic Canyon Project, Teledyne Engineering Services, Robert L. Cloud Associates, Roger F.
Reedy, Inc., Stone & Webster Engineering Corporation, and Designated Other Parties (as Observers).
June 17, 1983, Nuclear Regulatory Comission, Pacific Gas and Electric Company, Teledyne Engineering Services, Robert L. Cloud Associates, and Brookhaven National Laboratories.
o
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IDVP 8.2.2-1 FINAL REV 1 830815
J "R Trii:nYNE I ENGNEERING SERVICES O
July 21, 1983, Nuclear Regulatory Cormission, Diablo Canyon Project',
Teledyne Engineering Services, and Robert i.. Cloud Associates.
July 27, 1983, Diablo Canyon Project, Teledyne Engineering Services, and Robert L. Cloud Associates.
e r
~
e i
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8.2.2-2 '
REV 1 830815
- = %
REV 1 REV. O LATEST PEV. ACTliN PG1E 830817 0.3-5 VFILE NO. DATE BASIS REV. DATE BY STATUS OWG TEs~ MODS SUBJECT NIE E6F IE5' VALVE 5805B ORIENT. LINE 1988, AUX. BUILPING.
5 N ii6 'iii~ "i" 5fiii3 Ti5 ER/A 938 COMEhT! VALVE 88053 WILL BE ROTATED TO VERTICAL POSITION REQUIRED BY PGLE DRAWING DC663219-458-2(ERROR ESTIN8 HOUSE LETTER FME-4735 (821026) PERMITS VALVES 8725A, 8724A AND 8728A TO BE INSTALLED IN HORIZONTAL DIRECTION (CLOSED llEM). ALSO IN ITR 12.
UEUE8805B ORIENT. LINE 1988. A'JX. BUILDING.
" Tii 'RE0E20 ~flii ~~ii ii3'0F1 TES CiE"' iECA 55IF IEE COMENT: VALLE 8305P WILL fiE ROTATED TO VERTICAL FOS?T10N REQUIRED 4Y PGIE DRAWING DC663219-45 FIR $liS VM.VES f.126As 8724A AND 8728A 10 EE INSTALLED IN HORIZONTAL WrSTIh6H00SE LETTER FfAE-4735 (821026)
DIFECTION tCLOSEb ITEb'. ALSO 14 IIR 12. RLEA TO FIELD VERIFf COMPLETED MOD INDICATED BY DCP 830720 COM 938 0 . 9 0 COMENT: SPACE ESER'KD FOR LATER REVISION.
l 1
938 0 10 0 COMMENT: SPACE RESER'KD FOR LATER REVIS10N.
COMENT: SPACE RESERVED FOR LATER REVISION.
938 0 12 0 COMMENT: SPACE RESERVED FOR LATER REVISION.
938 0 13 0 p COMENT: SPACE RESER'KD F0R LATER PEVISION.
U 938 0 14 0 COMMENT: SPACE RESCRWD FOR LATER REVISION.
939 87^129 FID 0 8 & l20 RL GM f RtIARDe SFT,73-72C 51RfCII0ih LlHE 1Fd8 FL IdlLflh6.
COMMENT! ISE 446544 KV.11 %% SLPFORT 73/721r10 3E r.Thi IN d-i DikiC11tW Urili! MELD INSfECl!0W W)WS SUPP'$T 10 BE ACTI'E IN P3iH N-S 1 E-W D! REC 11 HS. .
939 820120 FID 1 - 820519 PLCA PER/C TES RDF SlFT.73-72R DIMCTION. LINE 1988, AUX. B91t DING.
COMENT: itLCA 102 WAYS 13 SCWED ALL STRESSES LESS THAN eLLOWABLE. FG1L ANAL 1 SIS 8-25 SHOWS 9RORT MilW IN W-S DIRECTINI OM,Y 939 5 55 5 75E I E 556d i T 5 E57 I d iE E ~ SIEi~73-72R 2IRECT10A LI M 1988. AUX. BUILDING.
CCMME/.T: IIR-1, 3.2,4 i PG1E LETTER DCVP-Rt.CA-74 DATEli APPit. 23, 1982 ( PLCA F!lE P105-4-937-00f).91E PIPiWG A% LYSIS 8-25 ktCA FILE P10M-432).RLC4 PIPl% ANALYSIS RLCA 102. SUPPORT ACil'd IN THE W-S 1 E-W DIRECTICN. ALL PIFE STRESSES LESS THANetLOWA3tES.
939 82'0E26 ~FIF ~ 820708 TES CR 'N5NE Ed I E SUPT,73-72R DIRECTICN. LINE 1988, AUX. BUILDING.
COMMENT: SLP1. 73/7'M ON CVL ISO 446544 R11 AND DESIGN ANALYSIS 8-25 IS SHNN AS X-DIR SUPPORT. FIELD INSPECTION INCICATED SUPT. IN X-Z DIRECTION. RLCA 102 ANALYSIS SHOWS STRESSES LESS THAN ALLOWABLE. PG1E LETTER DCVP-RLCA-74 (820423 AGREES WITH FIELD INSPECTION. ERROR CLASS C. NO PHY. MODS. PER PGLE RESOLUTION SEET 820701.
~ 5 6~ 820120 FID ~6~ 526i5 RLCA DiR~~ E(CARif Eiili~i63 DIMENSION. TlRBINE BUILDING.
' C0lWtiMT: ISO 449316 REV.3 SHOWS 'AS-BUILT' LENGTH OF LINE 103 SOUTH OF SUPPORTS 18/2R 1 18/12SL AS 15 FT,6 INCHES. RLCn FIELD INSPECTIDM SHO'KD DIMENSION AS 6 FT.
940 E20120 FID '-1 820510 RLCA PER/C TES RDF LINE 103 DIMENSION.' TURBINE BUILDING.
COMMENT: TIE DESIGN ANRYSES 4-214-3 DO NOT SHOW CORRECT DIMENSION. PIPE STRESSES IN RLCA 102 ANALYSIS DO NOT EXCEED ALLOWABLE.
U(3 1.......-_..'__. .. * ...... ... ... ....
940 B20120 FID '2. 820619 TES ER/C P01E RDF [.kNE103 DIMENSION.TURBINEBUILDING.
COMMENT: IIR-1, 3.2.4 i PS1E LIR DCVP-RICA-20 (5/2/82) (RLCA FliE P105-4-940-003). PIPING ISO 449316, REV.03 ( RLCA FILE -
P105-8-454) P COMPUTERk3sed.GIE K15RF7J (RLCA PIPING FILE' ANALYSIS 4-2 (RLCA P105-4-521-045).ALL STRESSES FILELESS P105-4-432).14-3(RLCA THAN ALLOWABLE. DIM DIFF.FILEEXCEED P105-4-432).RLCA PIPI 79-14 TOLERANCE.
~~
/
REV 1 m REV. 0 LATEST REV. ACTION PG1E R30817 0.3-9 FILE NO. DATE BASIS REV. DATE BY~ ~ 5iiiis' iiRE~iis MODS SUBJECT 950 820128 FID ~6 820701 Ti5 PkETCI ii5 ~5i iii hilhilCV95PLATETHICKNESS. AUX. BUILDING.
COMENT: ITR-le 3.'.1.3, PHYSICAL MODIFICATION COMPLETE IES SITE VISIT
SUMMARY
e 820625.
950 820128 Fi6~ ~ E 820701 T55 CR- s50E Ei iE5' YALVE FCV 95 PLATE THICKNESS. AUX. BUILDING.
COMENT: FIELD INSPECTION SHOWS LWDERSIZE PLATE IhST ALLED ON FCV-95. DCO-G-M-876 REQUIRES 1/2 INCH PLATE. 3/8 INCH PLATE INSULLEB. PHYSICAL M0D. PER PS1E COMPLETION SHEET 820713 CORRECTED DISCREPENCY. ER/Ce ALL STfESSES ELOW ALLOW /# l 'JIk lM WITHOUT h0D.
~ ~
950 820129 FID ~ E 830422 Ti~S DIR ELCA )CI EES VALVE FCV 95 PLATE THICKNESS. AUX. BUILDING.
COMENT: MODIFNITION Cr 1/2a STIFFENER PLATE TO VALVE FCV-37 PER DCD-G-M-876 NOT IMPLEENTED. FIELD OBSERVED TO HAVE .
PLATE 5. CONCERNED 3ESIGN ANALYSIS FOR TESE VALUES MAY NOT REFLECT AS-BUILT CONDITION. RLCA TO REVIEW AND l PRO RECOMENDATION FOR FUTIRE DISPOSITION.
~
930 820128 75E ~ E 830429 RL'CA PPRR/0IP_ fE5 Ei iE5' QiEUE7CV95PLATETHICKNESS. AUX. BUILDING.
COMENT: BURING FIELD VERIFICATION BY IDVP FOR OTER EQUIPMEWT, OBSERVATION THAT FCV-37 STIFFNER PLATES WERE 3/8' NOT 1/2' PER DCO-G-M-B76. DESIGN ANALYSES FOR THESE VALVES MAY NOT REFLECT AS-BUILT. PG1E TO REEXMIhE AS-BUILT MD RESPOND.
~
950 820128 FID 'iE 830504 TE5 F?IEDIP i'GIE 5i Ii5' VALVE FCV 95 PLATE THICKNESS. AUX. BullDING.
COMENT DURIN6 FIELD VEMFICt. TION BY IDVP FOR OThER EQUIRENT CBSERVATION THAT FCV-37 STIFFNER PLATES WERE 3/8' N01 1/2' 'ER DCO-G-M-676. DESIN ANALYSES FOR THESE VALVES MAY NOT REFLECT AS-BUILT. PG1E TO
~
REEXMINE AS-BUILT AND RESPOND.
~
950 ~820l55 lie 'iE 830608 TI5 OIR hiCA 5i ilf VALVE FCV 95 PLATE THICKNESS. AUX. BUILDING.
COMENT: DESIGN ANALYSIS FOR TESE VALVES MM NOT REFLECT AS-BUILT CONDITIONS. TES REQUESTS RLCA TO VERIFY THAT 1/2' PLATES HAVE BEEN INSTALLED ON THE SEVEN VALVES INCLUDED IN DCO-G-M-876.
%U 320123 'IID ~'
12 8'30i12 FICA FNUl IE5 ~5i iii hiLU53CV 95 PLATE THIChNESS. AUX. BUILDING.
ueFNT: REfFNI htf A FIFLD VEFIFICATION SHOC All AVES 5FECIFIED IN DCD-G-M-876 AS HAVIhG 1/2' THiCh STIFFNER FtATES INSTALLED
/,} 10 NOU Pf Flf CT THE DESIGH CONDITICNS FEF THE DCO.
U 950 8?01 5 illi ~ E 5555 ' TES f Ek 'E l' '
1 IES U 755' 050.I5TLV95PLATETHIChNESS. AUX. BUILDING.
(OnMENT: RECEN1 ELCA FIELD VERIFICA110N SHOWS ALL GlVES SFECIFIED IN DCO-G-h-876 AS HAVING 1/2' THICL SilFFNER FLATES INSTALLED 10 NOW FEFLECT THE DESIGN CONDITIONS PER THE DCO.
^
" 9" O U0th 'iili li 8507i5 TES CE ~i[NE N Si IEU UELEElCV 95 FLATE THICANESS. AUX. BUILDING.
COME NT: nolilFIC ATION OF 1/2' STIFFENER FLATE 10 VALVE FCV-37 FER DCO-G-M-876 NOT IhFtEMENTED. FIELD OFSERVED TO HAVE 3/8' PLATE COREFN THAI D. A. FOR VALVE 5 nAY NOT RUtECT AS-PUILT CONDITION. EECENT PLCA FIELD VERIFICATION SHOWS ALL VALVES SPEC-IFIED IN DCO-b-M-876 AS HMNG 1/?' THICL SilFFNER FLATES INSTALLED TO NOW REFLECT THE DESIGN CCNDITION. LAS ER/C. CI.
951 820129 FID --- 0820129 RLCA DIR RLCA RDF SUPT. 1-27 LOCATION.LINE 593, AUX. BUILDING.
CLMMENT AUXILIARY FEEDWATER ISO 445878 REV.14 LOCATION OF SUPPORT 1/27R DISAGREES WITH FIELD INSPECTION LOCATION.150 S10fS DIMENSION AS 9 INCHES FROM ELBOW. RLCA FIELD INSPECTION SHOWED 35 INCHES FROM ELBOW.
~
951 85iN 7[U' I
~1" 820309 RLlA PfREIUiV T'[S RDF SUPT.1-27 LOCATION.LINE 593. AUX. BUILDING.
COMENT: PGLE PIPING ANALTSIS 2-17 LOCATION DISAGREES WITH FIELD INSPECTION LOCATIONi PG1E ANALYSIS SHOWS DIMENSION AS 33.25 INLFES FROM ElBCW. PG1E TO kEVISE ISO.
951 820129 FID ~~ 2 820417 TE5 PRR/DEV PG'5EREF SUPT. 1-27 LOCATION.LINE 593s AUX. BUILDlHG-COMENT: PGIE PIPING ISO 445878e REV.14 i PGIE PIPING ANALYSIS 2-17 DATED 5/7/82. INFORMATION INCORRECT ON ISO. FIELD AGREES
- p. WITN DESIGN ANALYSIS WITHIN 79-14 TDLERANCES.
951 8?012? FIP 3 820024 TES CR NONE RDF NO SUPT. 1-27 LOCATION.LINE 593, AUX. BUILDING.
COMENT! SUPPORT 1/27R IS SHOWN O't ALX. FEEDWATER 150 445878 REV.14 TO BE LOCATED 9 INCHES FROM THE ELB0W.RLCA FIELD IN k SHOWED THIS SUPPORT TO BE LOCATED 35 INCHES FRCM THE ELBOW. DESIGN ANALYSIS 2-17 (820507) SHOWS SUPPORT 1/27 LOCATED 331/4' FROM ELBOW (WITHIN 79-14 TOLERANCE) DEVIATION. NO PHY. MODS. PER PGIE COMPLETION SEET 820521.
l
\
l t REV I REV. 0 LATEST REV. ACTION PGtE tug ;) 7 qi,,;-h) l FILE NO. DATE BASIS REV. DATE BY SiETUE ORG TEE MODS SUBJECT 982 ~'2i2E6 8 DMD ~'4 E2Ef2I R5A PIEECi ii5 RE ~~ IEREiiDG RUME TRMSMITTALS CWWENT: ITR-le 3.1.4 THIS EDI TO E COMBINED WITH EDI 1026 AS M ERROR A OR B.
982 820206 MD T 820723 TE5 PRR/CI' TE5 RDC ~~ TlRB KD6 BLUME TRMSMITTALS C0KNT: DELETE FROM ITR-1, 3.1.4 THIS E01 IS COMBINED WITH EDI 1026 AS M ERROR A OR B.
982 ~i206 82 DMD 7 820723 TIES CR ikiNE EEC IE)~ EUEE5LDGKUMETRANSMITTALS C0 K MT! SECTION 3.3.3 0F NOV. 12, 1981 PRELIMINARY SEISMIC REVERIFICATION REPORT STATES THAT DETAILED TRANSMITTALS ERE NOT REVIEED BY RLCA. BUT SINCE TE TURBINE BUILDING IS KING EVALUATED AS PART OF THE PG&E ITPe THIS E01 IS E0MBINED INTO 1026 (ER/AB).
983 820206 SID 0 820206 RLCA PER/A TES RCW RACEWAY SUPPORT SPECTRA C0KMT: NINE OF TENTY RACEWAY SUPPORT SEISMIC CALCULATIONS DONE WITH INAPPLICARE SPECTRA.
983 820206 SID 1 820421 TES ER/A PGtE RCW RACEWAY SUPPORT SPECTRA C0KNT: ITR-1, 3.7.4 NINE OF TENTY SUPPORT: CALCULATION DONE WITH INAPPLICAKE SPECTRA.
983 820206 SID ~~~ 2 820910 T55 ER7E P55ERfU [5' RACEWAY SUPPORT REMALYSIS C0KNT: NINE OF TENTY RACEWAY SUPPORT SEISMIC CALCULATIONS DONE WITH INAPPLICABLE SPECTRA.
REV 2 ISSUED TO COMBINED EDI FILES 910 MD 930 INTO THIS ONE FILE AS A CLASS 'A' ERROR.
1 53 " 5 M 0h 'ilii ' ' i' 5505U TE5 O!E" ~ EUA ECU 555' EEC5UhiSUFFORTREANALYSIS CCMMENT: M CA 10 FEVIEW THE DCP CCMFLETION PACKAGE 3 AND SUPMIT A POTENTIAL RESOLUTION GR ERROR REPORT TO THE PROGRM MANAGER.
983 0 4 0 COMENT: SPACE RESERVED FOR LATER REVISION.
983 0 5 0 COMENT: SPACE RESERVED FOR LATER REVISION.
COMENT: SPACE RESERVED FOR LATER REVISION.
984 820206 DMD T E20206 RLCA DiR k'LCA EDE ~~ TURB BLDG INTERFACE PROCEDlRES COMMENT: TE PGtE DESIGN REVIEW IS PRESENTED IN THE REPORT 'HOSGRI DESIGN VERIFICATION - TlRBINE BUILDING'eFEBRUARYe1920 (LOG 7).
SINCE TE DESIGN REVIEW DID WOT VERIFY TE INTERFACE PROCEDURES BETEEN URS/BLUME, PGLE AND TE FIELD (FIG 4-10-2e URS/
K UME REPORT ON DESIGN REVIEW, LOG 7), THESE WILL BE INVESTIGATED .
984 820206 DMD 1 820618 RtCA PPRR/OlP TES RDC TlRB BLDG INTERFACE PROCEDURES COMENT: ESIDES PEV.0 CONCERN, TE KUME INTERNAL REVIEW IDENTIFIED PPOKEMS WITH TE ANALYTICAL MODEL.
984 820206 DMD T 820701 TEE PEEI0if P'GIE EE ~ TlRB BLDG INTERFACE PROCE9tRES COMENT: ITR-1, 3.1.4 MD PGLE ITEM 24 MAY INDICATE NEED FOR REANALYSIS. PREVIOUS PGIE DESIGN REVIEW BID NOT VERIFY PGLE/KUME FIELD REPORT. INTERFACEi THIS STILL RE0 VIRES VERIFICATION IF NO REANALYSIS IS DONE. TES REVIEWED RtCA NOV. 12 198 984 820206 DMD 7 820720 T55 OIE'~ iiCA R E ~ ~ TURB K DG INTERFACE PROCEDURES O)
COMMENT: BUILDING.ITR,TES AND 31.4 ELCABASED ON PGtE WILL RECONSIDER MD RESOLVE INTERNAL THIS FILE. TECHNICAL PROGRM PRESFNTED ON J PGLE MAY REANALYZE TIRBINE 984 820206 DMD 4 B20721 RLfCA PPRR/CI i5S EDf TlRB BLDG INTERFACE PROCEDURES COMMENT: ITR-le 3.14 RLCA RECOMENDS COMBINING THIS FILE WITH EDI 1026.
REV. 0 LATEST REV. ACTION PG1E 8 7 D.3 26 RILE NO. BATE BASIS REV. DATE BY STATUS ORG TES MODS SUBICT
~I002 ~ 820206 SID ~ E 820623 Ti5 PRR/CI il5 INi ~M ~ SUPPLY FANS S67, 68, 1 69 IlFUT ColOENT! KCA HAS REVIEWED CRCULATIONS ATTACED 10 P6E ACTION SEET OF 820310 AND ALSO VERIFIED THAT NO MDIFICATI(BIS HAVE KEN MADE AS A RESULT OF THIS FILE.
HOME "CIE E0~ SUPPLY FANS S67, 68 1 69 INPUT 1002 820206 SID ~ E 820623 TEE E CR COMIENT! RLCA PELIMll1ARY REPORT OF 811112 NOTED CALC'S FOR FANS USED UNCONSERVATIVE SEISMIC INPUT. ERR PGE PROVIKB IEW CRC. WITH PROPER INPUTS. IDVP VERIFIED NO MODIFICATION MADE AS RESULT OF THIS FILE.
SUPPLY FANS S67, 68 1 69 INPUT 1002 820206 SID 6 830308 TES DIR RLCA C* NO C0lIENT! BASED ON P8E RESPONSE AND RLCA VERIFICATION THAT NO MOBS REQUIRES, RLCA SHOLLD CONSIDER ISSulN6 POTENTIAL PROGRAM RESOLUTION REPORT WERE ER/B IS DOWNGRADED TO ER/C AND FILE CLOSED OUT. REFER TO PAR. 5.1.2 0F 8301 IDVP PROCEDIRE.
~NE" 55Ni.EFMS S67, 68169 IIFUT 1002 820206 SID ~ E 830310 RLCA PiiTC" il5 INi COMENT: CRCS 'JSED INCORKCT MB WCONSERVATIVE SEISMIC INPUTS. ALSO, FORCED DRAFT SWTTER DAMPER OURIFICATION SHOED IKERECT SEISMIC DEFINITION KCAUSE GRAVITY WAS NOT ADDED TO VERTICAL ACCELERATION. STRESS CALCS USING CORREC AND KFINITIONS DIBil'T EXCEED RLOWARES. DOWNGRADED FROM ER/B.
~
820206 SID ~ f 830322 T 5 ER/C NIE 6E 00~ SUPPLY FANS S67, 68 1 69 INPUT 1002 ColWENT: CRCS FOR SWPLY FANS FOUND TO USED INCORRECT MD WCONSERVATINE SEISMIC INPUTS.ALSD, ORAVITY NOT ADKD FOR SEISMIC CollSIDERATIONS OF FORCEB BRAFT Sit!TTER DAIFER 00E. CALC STRESSES 'lSING CURRElli SEISMIC INPUTS AND DEFINIT EXCEED RLOWAKES. ER/B ESTAKISED BT REV.1 TO THIS FILE IS DOWNGRAKD.
1002 E263E6 ~5if " E 830322 TE5 Ci~~~ "NUECAK 6~ SUPPLY FANS S67, 68 1 69 INPUT ColOENT: CRCS FOR SWPLY FANS FOLBID TO USED INCORRECT AND UNCONSERVATINE SEISMIC INPUTS.RSO, GRAVITY NOT ADDED FOR SEISMIC CONSIKRAT10llS OF F(RCED BRAFT SWTTER DAffER QUAL. CALC STRESSES USING CURRENT SEISMIC llFUTS AND KFINITIONS D EXCEED ALLOWABLES. ER/B ESTAKISED BY REV.1 TO THIS FILF IS DOWN6RADED TO AN ER/C.
1003 E26 5 5 OD ~~0 820206 R EA OIR liEA 6 ~ E W RM HVAC DUCT SUPT p CGIGENT: MS8R1 BUCT SWPORT 00KIFICATIONS HAVE NOT BEEN LOCATED AS OF B11029. TO K ADDRESSED BY PG1E 1 REVIEWED
(,y BY RLCA.
1003 820206 OD "i 820607 RLCA PPRR/0!P TES ECil - UKi[SERMHVACDUCTSUPT COMEllT: P6E WILL SLPPLY TE ANALYSIS OF RECORD DATED PRIOR TO 811028 1003 820206 OD 2 820621 TES PRR/0IP PG E RCW 4 KV SW RM HVAC DUCT SUPT C019ENT: PGE TO SUPPLY TE ANALYSIS OF RECORD DATED PRIOR 10 811028 1003 820206 OD 3 820823 TES DIR RLCA RCW 4 KV SW RM HVAC DUCT SUPT C019Elli: RLCA TO REVIEW AND DISPOSITION ACCORDINGLY TE /61E RESOLUTION 1 COMPLET10N SE ETS, 820615 1003 820206 OD 4 820825 RLCA PER/C TES RCW 4 KV SW RM HVAC DUCT StPT COMMENT DUCT SLFPORT CALCS. DATED PRIOR 10 811029 DO NOT QUALIFY SUPPORT FOR AREA A (ItRBINE BUILDING). DUCT SlFPORT WAS NOT EVALUATED FOR HOS6RI.
1003 820206 OD ~ E 821005 T55 ER/AB~- 5IE ECII iii HVAC DUCT SUPPORT REEWLUATION CD10ENT: REV. 4 WAS A PER/C. BASED ON 820917 SUBMITTAL OF DCP PHASE 1 FINE REPORT IN WHICH DCP HAS STATED THAT HVAC SLFP(fits ARE KING REANALYZED, IDVP PROGRAM REVIEW COMMITTEE ON 820929 KCIDED TO CHANGE THIS TO All ERROR /A OR B. IDVP ALSO ,
KCIKD TO COMBIE FILE 1077 WITH THIS FILE. t
'i463 " 5MN5 '65" T 536Ni tie Gii ~ FRA 55U ~ AUEf'60CT SUFFORT FEEVALUATION C0t'NENT; IMFD ON IDVf VERIFICATIO" FFF0FT 06 CAP TO DATE, IDVP HAS ONLY ONE UNRESOLVED ISSUE. E01 !!34, WHICH WILL BE M M e li :H ARATEt Y. 5.t rA 1ll Ff vtEW 3D f f t0LVE f lLE 1003, WITH EXCEPTION OF E01 1134 ISSUE, IF POSSIBLE.
"I0di' 320IN Oli T BI0'75 kliA FIRfdCI il5 REU ~ E9hC iiUCT SUPPORT FEEVALUATION
~
COMENT: IDVP HAS VERIFIED THAT WITH ikE EXCEFTION OF SFECIFIC ITEM DETAILED IN E011134, WHICH WILL BE RESOLVED SEFARATELY, CAP F0P WAC DUCT AND SitFP0FiS IS AN ACCEPTABLE AND FROPEPLY IMPLEMENTED FROGRAM FOR RESOLUTION OF E011003.
"iO6i" 55 55 ~55" ~'5' Ei5Edi TE5 FIE?ft' iE5 (fU 00EC 60CT SUFFORT REEVALUATION COMFNT: THE IDVP HAS VFRIFIED THAT EXCEPT F0fi ISStF IN E01 1134. THE CAP F0F HVAC DUCT AND SUPPORTS IS AN ACCEFTABLE AND f kCf ERt , MPt FhfNT[D FRfifMM FOR FESOLUTION OF E01 1003. E01 1134 WILL EE RESOLVED SEFARATELY.
PGIE 830817 0.3-27
___..[_______
FILE NO. __DATE BASIS REV. DATE BY STATUS DEG. _ ..TESMODS SUBJECT
~
'100I U?O N 'GiI ~ f I60Nat If r, gg pus; igy fdj- isit ii!CI '.UffuRT Ef f 9All'ATION rDMfNT liUCI NillMI LA105 DAllii IRIDF 10 191 0 tw I huAl tl Y WiURI F0F ALF A A bl IURHNE I< Ult tilHG. I'UCI SUf f 0RT EDI FVALUAltD F0F HZGRI. I FlDDES L01 10?/. tbvP vikif 110. t (ff t1 IGF IEUF IN 1134 UP !CR llVAC 0001 MD Suf PORTS IS A ACCEPTAM! ANb if Of EFLY IMFLEnlNTED lEnGEM !OR Ft.E0t UlluN OF 101 1003. E01 1134 0 820206 RLCA OIR RLCA RW PGIE-E STINGHOUSE SEISMIC INTERFACE.
1004 820206 OD COMENT! RLCA PREL. REPWt1811112.ELECTRICE EQUIPMENT MD INSTRUMENTATION. CONCERN AD SEISMIC INFORMATION FROM P6tE TO WESTINGHOUSE.ONLY ONE TRANSMITTAL FOUND TO DATEINE FOR CONTAINENT INTERIOR.
1004 i2'056 OD ~ E 826i22 RiCA FEREE0iP ii5 ki ~ Sii-U[STINGHOUSESEISMICINTERFACE.
00KMT RLCA RECOMMENDS THAT PGLE ASSEMRE 1 CONTROL SPECTRA AND CECK 00ALIFICATIONS A6AINS 1004 820206 OD ~ E 820417 TEi PfE55P 5iE EE ~' EiE~EISTINGHOUSE SEI';MIC INTERFACE.
COMENT: PGLE TO ASSEMKE t CONTROL SKCTPA : D CECK QUALIFICATIONS AGAINST THIS SPECTRA.
3 820524 TES DIR RtCA RW PG1E-WESTINGHOUSE SEISMIC INTERFACE.
1004 820206 00 COMENT: PGE RESOLUTION SHT. 820521 WITH INDEX OF l'0GGRI SPECTRA PCCEIVED BY WESTINGHOUS TO TES DOCUMENTATION THAT CONFIRMED THIS INIEX. WESTINGHOUSE AUDIT ON 820507 BY IDVP.
1004 5i0iO6 OD ~ I 820609 RtEA PUE/Ci il5 RI ~ Nii-U5STINGHOUSESEISMICINTERFACE.
COMENT: BASED ON P6tE TRANSMITTE DCVP-TES-72 AND TK IDVP WESTINGHOUSE AUDli DN 820507, TES INFORMED RLCA THAT SEISMIC INTERFACE BETWEEN PGE MD WESTINGHOUSE IS VERIFIED.
~'
1004 820206 OD 5 820622 TE5 PER7Ci~ UE5 Ri - FG1E-WESTINGHOUSE SEISMIC INTERFACE.
00KNT: BASED ON PG1E TRANSMITTAL DCVP-TES-72 MD THE IDVP WESTINGHOUSE AUDIT ON 820507
% TES CONCLUDED THAT TE SEISMIC INTERFACE ItETWEEN P6tE MD WESTINGHOUSE IS VERIFIED.
1004 5 [020E OD "i 820622 TES di~ ~ IEiNE Ri itii' EGIEUESTINGHOUSESEISMICINTERFACE.
COMENT: ELECTRICAL EQUIPENT MD INSTRUMENTATION. CONCERN ADDRESSED INSUFFICIENT TRANSMITTAL OF S TO W. BAeED ON PGLE TRANSMITTAL DCVP-TES-72 AND THE IDVP WESTINGHOUSE AUDIT ON 820507r TES CONCL INTERFACE BETWEN PGIE MD WESTINGH0' J SL IS VERIFIED.
~~
1005 820206 OD ~ I 820206 RL'CA die ~ RL'CA Rili WYLE LABS TRMSMITTAL OF SPECTRA COMENT! DOCUMENTATION REDVIRED REGARDING FORMAL TkAHSMITTAL OF SPECTRA FROM PGE TO WYLE LABS.
1005 820206 OD ~ E 820309 RICA PPRR/CI }E5 iiR5 ~~ EYEE ABS TRMSMITTAL OF SPECTRA COMMENT: NO DOCUMENTATION FOUND TO DATE REGARDING FORMAL TRANSMITTAL OF SPECTRA BUT CONCERN COVER
~ ~ ~
1005 82656 OD 2 820417 TES Ci ~ E EE E E ~ WYLE LABS TRANSMITTAL OF SPECTRA COMENT! ALTHOUGH NO DOCUENTATION OF FORMAL TRMSMITTAL OF SPECTRA FROM PG1E TO WYLE HAS BEEN FOUND TO DAT COVERED BY EDI'S 1013 1 1049.
~~
1006 820206 OD ~i 820206 RUCA OIR RL'CA i'5iK ELEC EQUIP GUAL. BY ANALYSIS COMENT: FOR EQUIPENT REQUALIFIED BY ANALYSIS, AS INDICATED BY NOTE 5 IN TARE 10-10F HOSGRI, NO INFORMATION HAS KEN FOLMB TO DATE AS TO WHO HAP PERFORMED TESE MALYSES. THIS IS BEING COVERED GENERICRLY BY RLCA IN THE CURRENT PROGRAM.
1006 820206 ~5E' ~ E 820309 R[CA PPRR/CI iES liiK ~~ ELEC EQUIP OUAL BY ANALYSIS COMENT: TE PHASE I PROGRM INCLUDES TWO ELECTRICAL CABINETS QUALIFIED BY MALYSIS.
~ ~
1006 820206 09 ~ E 820 5 TES CR EEE Cid E" ELEC EQUIP QUAL BY ANALYSIS COMMENT: FOR EQUIPMENT REQUALIFIED BY ANALYSIS, AS INDICATED BY NOTE 5 IN TABLE 10-10F HOS6Rio NO INFORMTON HAS KEN O \
( FOUND TO DATE AS TO WHO HAD PERFORED THESE ANALYSES. TE FHASE I PROGRM INCLUES TWO ELECTRICAL CABINETS v/ QURIFIEB BY ANALYSIS.
1007 820206 ~5if ~ T 820206 RLCA DIR ItICACIK - ELEC EQUIP TRANSMITTAL OF INFO C0KNT: SHOED FlRTER IWYESTI6ATION FAIL TO UNC0YER RECORDS THAT UNSATISFACTORILY B001 BENT TE TRANSFER OF SEISMIC REQURIFICATION IEORMATION BETWEEN PGlE MD TEIR CONStR.TMTS, THE ACTUAL TEST SPECTRA MD TE REQUALIFICATION ANALYSES WILL BE EXAMINED TO SEE IF APPLICABLE SEISMIC IEORMATION WAS APPLIED.
l
( EV. O LATEST REV. ACTION P61E 83 8 7 D.3-33 FILE NO. BATE BASIS REY. DATE BY STATUS ORS TEs' MODS SUBJECT 1020 820218 SIB T 820417 T55 PRR/DEV N IE Y i ~ ~ 5 E 55ETWATER PUMP PRELIM SPECT. INTAKE STRUCT.
ColOENT: PRELIMINARY SPECTRA IDENTICAL TO HOSORI SPECTRA C0lFIRED, TES TRIP REPORT N01449.
~
1020 E262E8 SIB 3 820629 TES CR ilENE 70'T 50 0 ' AUX SALTWATER PtMP PRELIM SPECT. INTAKE STRUCT.
ColOENT! LIlCONTROLLEB PREllMIMRY SPECTRA USED TO QUALIFY PUMPS PSE FILE 116.3,771227. IKMTICAL TO HOSGRI SPECTRA,PSE ColfLElION REPORT 820601. DEVIATION.
~'
1021 820218 OD 0 820218 1[CA OIR [UA Rif ~ CCWHX ANALYSIS AS RIGID ANCHOR. TURBINE K B6.
COMIENT P61E PIPIllB AllALYSIS 4.3 SHOWS COEONENT COOLING WATER EAT EXCHANGER AS RI6IDI 10SSRI (TAKE 7-5) LISTS IIAllRAL FRED.
(F 9 Hz. (HORIZONTAL AllD VERTICAL) FOR THIS HX. THE MODELING OF A NONRIGID PIECE OF EQUIPENT AS A RIGID ANCHOR MY NOT E CONSERYA11YE.
1021 820218 OD T 820430 RICA PitR/0lP ii5 iid ~ ~ CCWX ANALYSIS AS RI6ID ANCHOR. TtRBINE KBG.
C019ENT: PER P6E SEMI-MONTILY OPEN ITEM 922- PSE WILL EXMINE TE RIGID M0KLING OF TE CCWHX IN TE PIPIII6 ANALYSIS.
1021 820218 09 T 820510 TE5 PRR/0IP 55E EE ~ CCWHX ANALYSIS AS RIGID AllCHOR. TURBINE BLD6.
ColOENT! ITR-1, 3 2 4 P6E PIPillB AllALYSIS 4-3 DATED 1/30/80. HOSGRI REPORT TABLE 7-5. TE NATLRAL FREQtENCY OF TE CCW IEAT EXCHA116ER IS LESS THM TE MINIIRM REQUIREENT FOR PIPING MODEL TERMINATION. P6E SHOULD EXMIE THIS PROKEM.
~
1021 820218 OB T 820910 TE5 DIR ELCA EE - CCWHX ANALYSIS AS RIGID AllCHOR. TlRBIIE KDS.
C010ENT: BASEB ON PGE PRESENTATIWS (ALRIST 4,1982 AND AUGUST 26,1982) 0F TEIR INTERNAL TECHNICAL PROGRM OF PIPIllG TES MD RLCA WILL RECONSIER t0MBIlllll6 THIS FILE WITH FILES 961,1058:1059 1 1098 INTO ONE ERROR CLASS A OR B FILE.
1021 820218 OB T 820913 RECA PPRR/CI I[S EEF CCWHX ANALYSIS AS RI6ID MCHOR. TlRBINE KD6.
O COlGENT: THISBASEB FILE COMBIED(31 WITHPOE PRESENTATIONS FILES (406 961,1058 1059, MD 1098 INTO DE6ERROR AllDCLASS AU6A26,1982) 0F TEIR INTERNAL TEDellCAL P OR B FILE. SEE FILE 1098 FOR ERROR REPORT.
1021 820218 OB ~ 3~ 820921 Tli Pitif/fl~ il5 RiiF ~ "CI'WAIAMALYSISASRIGIDANCHOR.TURBINEBLB6.
ColgENT: PGE PIPING AllALYSIS 4-3(800130). HOSBRI REPORT TABLE 7-5. TE NATtRAL FREQUENCY OF TE CCW EAT EXCHM6ER IS LESS thall T)E MIllllRM REOUIREENT OF PIPING MODEL TERMINATION. THIS FILE HAS KEN COMBINED INTO FILE 1098 MD HAS BEEN E SI641ATED AS ERROR A/B.
1021 820218 OD T 820921 TE5 CR E6IIE if E6~ CCWHX AllALYSIS AS RIGID ANCHOR. TURBINE KPG.
COMENT! P6E PIPING ANAL 64-3(REV 16,3/4/80) REPRESENTS TE C0f0NENT COOLING WATER HEAT EXCH. AS A RI6ID ANCHOR. TE NDSIRI RPi.
(TAKE 7-5) LISTS NATlRAL FREQ. OF 9 ERTI(HORIZ 1 VERT)FOR THIS KAT EXCH.TE MODELING OF A NONRI61D PIECE OF EQUIP.AS A RIGID ANCHOR MAY NOT E CONSERVATIVE. THIS FILE COMB.INTO FILE 1098 1 DESI6NATED AS ERROR A/B.
1022 820219 SID T 820218 RICA OIR ~[CA R iIiC - INTAXE STRUCTURE REEVALUAT10ll.
COMlENT SPECTRA AT 21' USED 8'-9'. SPECTRA APPLICABLE AT A LEVEL TEN FEET. BELOW UPPER PUE StPPORT ERE USEDi NOT CONSERVATIVE.
~ ~
1022 820218 SID T 820430 RLCA PNE/0iP T55 E5C IMTAKE STRUCTLHE REEVALUATION.
COMENT: P61E TO EVALUATE SPECTRA USED.
1022 820218 SID 2 820510 TES ' PRR/0IP P61E RDC INTAKE STRUCTURE REEVALUATION.
COBOENT! ITR-13.5.5.4 AND 3.9.4 PSE ASSEMEE SPECTRA. SPECTRA AT 2.1' USED 8'-9'. SPECTRA APPLICAKE AT A LEVEL TEN FEET.
ELOW LPPER PUMP SLFPORT WERE USEDI NOT CONSERVATIVE. P6tE TO EVALUATE SPECTRA USED.
~ ~
1022 820218 SID 3 820903 TES DIR RLCA RDC INTAKE STRUCTlRE REEVALUATION.
COMlENT: COMBIIE WITH FILES 967 8 988 RELATIVE TO EVALUATION OF INTAKE STRUCTURE SEISMIC SPECTRA. PGE TO REANALYZE INTAKE STRUCTtRE.
~
1022 820218 SID 7 820907 RECA PER/AB [ES ((C INTAKE STRUCTIRE REEVALUATION.
COMIENT: EANALYSIS OF INTAKE STRUCTIRE PERFORED BY PGtE, 820806 8 820901. COMBINE THIS ITEM WITH EDI 967 8 988.
"id23" 536)i5 'Si5 "5' 550950 155 Eid5E" NIE UC ~ iiiE5' STRUCTURE REEVALUATION.
00 MENT: SFECTM AT 2.1' USED 8'-9'.SFECTRA APPLICARE AT A LEVEL TEN FEET. EELCW UPPER PUMP SUFPORT WERE USEDi NOT C INTAKE STRUCTURE IN REANALYSIS IN PGIE INTERNAL TECHNICAL PROGRAM COMBINE E01 967 8 988 IN TO 1022.
.______-__-___-____a
l REY. 0 LATEST REV. ACTION PGE g 7 0.3-34 FILE NO. BATE BASIS REV. DATE BY STATUS ORG TES MODS SUBJECT
~
"lif2" i363i5 ~5ili " I 53 M i 155 015 ' ' ILCA fii "" iNIMESTRUCTUREREEVALUATION. SPEC!kA FOR -2.1' USED AS INPUI f 0R UPPER COMENT: UPPER AUX SALT WATER PUMP SUFFORI LOCATED 10' AliOVE ELEVAtl0N -2.1'.
59e9 FfP. SPECTFA uf '80T BE AmlCARE. %CA TO M.'IEW DCP t!-!ValuA!!0N 0F INtaf STRUC4kt StIW 9tV0M(0 "i6E2" 5F05ii '5llI " E 53 5 3 R'LCA PiiRTCi il5 IIIC "" iNTEi'STRUCTUREREEVALUATION.
COMMENT: IDVP HAS VERIFIED THAT WITH EXCEPTION CF SOILS WORhi WHICH WILL EE RESOLVED SEPARATELY, CAP FOR INTALE STRUCTURE IS AN ACCEPTARE AND PROPERLY IMPLEMENTED FP0GRM FOR RESOLUTION OF THIS E01.
i " i655 " 5565i5 ~556~ ~5' 55U56 T[5 FIUCi' IE5 E6C ~ isiE5'STRUCTUREREEVALUATION.
COMMENT: FILE REDEFINED TO TRACK DCP RE-EVALUATION PEING PERFORMED AS PART OF CAP. IDVP VERIFIED THAT WITH EXCEPTION OF SOILS WO% WHICH WILL PE RESCLVED SEPAPATELY, CAP FOR INTAKE STRUCTURE IS AN ACCEPTARE AND PROPERLY IMPLEMENTED PROGRAh FOR RESOLUTION OF THIS E01,
~
i652 " 5562ii '556~ T 55556 T55 CR- E65EE6C 'EU' INiiEESTRUCTUREFEEVALUATION.
COMMENT: UPPER AUX SALT WATER FtMP SUPPORT LOCATED 10' AB0VE ELEVATION -2.1'. SPECTRA FOR -2.!' USED AS INPUT FOR UPPER PUMP SUP PORT. IDVP HAS VERIFIED THAT WITH EXCEPTION OF SOILS WORK, WHICH Will EE RESOLVED SEPARATELYe CAP FGR INTAKE ST2VCTURE IS AN ACCEPTARE AND FROPERLY IMPLEMENTED PROGRAM FOR PE50tuTION OF THIS E01. INCLUDES E01'S 9671989. WAS AN ER/AB. Cl 1023 820219 OD 0 820219 RLCA OIR RLCA RDF 3' RVE DOClM. LIES 577 1 578, AUX. 196.
COMNTI P6tE BMG. 447119e REV.12 AllD PIPING SCEM. 102003 SEET 4 REV.9 REFERS TO ITEM 15 DN 102039. Thl3 BW6.102039. SHT.
41 REV.9 SHOUS 3 IN. VELAll VEVE TO K DESCRIED ON DWG. 663317-52. ONLY 414 IN. VELAN MVES ARE BESCRIKI ERE.
1023 820219 OB ~1 820322 IUCA PPRR/DEV TES itif "" EUELVE BOClm. LilES 577 1 578, AUX. 1 96.
C0lgENT! RLCA REC 0KlWED P68E CECK BOCNNTATION ON El VEVES. FOLLOWING PSE ACTitle KCA VILL SELECTIVELY VERIFT VRVE BOC N NTATION.
~
m 1023 820219 OD 2 820417 TUS PRR/0IP EilE EF ~ 3' VRVE DoctM. LINES 577 1 578, AUX. KDG.
(-) C010ENT: P6K TO CECK TE DOCUENTATION ON El MVES. FOLLOWIN6 P61E ACTION, RLCA WILL SELECTIVELY VERIFY M VE DOC N NTATION.
~
1023 820219 OD ~~3 820707 TES DIR ELCA id ~ ~ 3' VRVE DOCUM. LIES 577 8 578 AUX. EB6.
ColOENT! ITR-1, 3.2.4e' RLCA TO REVIEW IFORMATION SENT BY P6K 111 RESPONSE TO RLCA'S 820414 REQUEST.
~~ ~
1023 820219 OD 4 820713 RLCA PF1tR/CI i[5 RE ~~ 3' VALVE DOCUM. LIES 577 1 578 AUX. K D6.
C019ENT: KLETE FROM ITR-le 3.2.4, RLCA HAS REVIEVED TE IKORMATION REQUIRED TO MODEL TE AFV VALVE.
~
1023 820219 OD ~ E 820717 TI5 PitII/IE tis itii ~ 3'VELUEDOCLM. LINES 577 1 578. AUX. BLDG.
C019ENT: DC 66317-52-1. DC663317-4-3.102003 SEET 4, REV.9. PGLE VALVE INVENTORY NO. 102039. P61E PIPIN6 ISO 447119eREV.12. RLCA HAS RECEIVED TE INFORMATION REQUIRED TO MODEL TE AFW VALVE.
1023 820219 OD ~ [ 820717 TES CR ~ENE N Ed ~NO~~ 3' VALVE DOClM. LINES 577 8 578, AUX. K DG.
C0lWENT: RLCA WAS NOT ABLE TO 08TAIN INFORMATION FOR A 3 IN. VELM VALVE. THIS VALVE IS REFERED TO AS ITEM 15 DN TE AUX. FW. ISO 447119 REV.12. TE REQUIRED MVE DRAWING 643317-4-3 WAS LATER SENT BY PGIE TO RLCA.
1024 820220 FID ~i 820220 RUCA OIR itLCA E5 ~~~ PIPE StPT. N0l O .LINE 1917 EAUX BUILDING.
COMENT! PBSE MAKE-LPWATER ISO 449317e REV.3 MISLAKLS SUPPORT 855-40V AS 85S-40R.
~
1024 820220 FID 820520 RLCA PEtitICi iE5 RE ~~ PIPE SlFT. N0EN. LIE 1917 EAUX BUILDING.
COMENT: SEVERE LINES ARE SlPPtItTED BY THIS RESTRAINT: 5 RIGID MD ONE BY A SPRING HANGER.
THIS ITEM WILL E COVERED BY A REVIEW OF TE 79-14 PROGRM.
1024 820220 FID 2 820607 TES PRR/CI TES RDF PIPE SlFT. NONEN.LINE 1917 AUX BUILDING.
449317e REV.3 PSIE BRAWING 049272, SHEETS 44e44Ae45 Tlft006H 45D.StPPORT BW IS LABELED 85S-40V O ColeENT! P61E (SPRING PIPING MANGER) YETISO SIFPORT IS ACTUALLY A RI6ID Y FOR LIE 1917-4. SEVERAL LINES ARE SLFPORTED BY THIS RES RIGILY AND OE BY SPRING HANGER.THIS ITEM WILL BE COVERED BY A REVIEW OF THE 79-14 PROGRAM.
~
1024 820220 FID 820607 TIES CR iiiE Itii E0~ PIPE SUPT. NOMEN.LINE 1917 EAUX BUILDING.
ColWENT! ISO 449317 R3 SHOUS SUPP(Iti 85S/40R (RIGID). TK KSIGN ANALYSIS FOR THIS SlFPORT IS LABELEB 80S/40V (SPRIN6).
SEVER R LINES ARE SLPPORTED BY THIS RESTRAINT: 5 RI6I KY AND ONE BY SPRING. DRAWING 049272 SHT. 44,44Ae45A THitu 45D CONFIRMS SUPPORT FullCTION. CLOSED ITEM.
REV. 0 LATEST REV. ACTIDH PG8E
~ 8 0817 0.3-49 FILE NO. DATE BASIS REY. DATE BY STATUS ORG TES MODS SUBJECT 1068 820315 QAR 1 820524 TES CR NOIE MAR NO URS/EtBE GA FIMIN6S CO M NT: NO GA PR00 RAM IN CONFORMANCE WITH 10CFR50 APPEDIX 9e WAS IIPLEENTED: REStLTIll6 Ill LACK E FORitt KSIN CONTROL.
TO E REPLACED BY E0! 3005. CLOSED ITEM.
~
1069 820315 FID ~ i B20315 RLCA OIR ECAEDF - EEETCV 113/115 ta19tPT. AFU LIIES 577/578 AE . 3.
C019ENT: PGRE AFU ISO 447119e REV.12 SHOUS VALVES LCV 1131115 (BlSLFPORTED. RLCA FIELB INSPECTI0ll COIFIIBER THIS. PSE ANRYSIS 2-14 C0lFUTER DATE 1/16/82 INDICATES StFPORTS HAVE BEEN ADKD TO VRVES. RLCA TO ColFLETE VERIFICATION C"EB ON ORIGINAL FIELD INFORMATI0lle WITH SUBSEQUENT CONSIKRATION OF REVISIONS.
~~
1069 826315 FID ~ I 820426 R E A PPRR/CI 55 EE VALVE LCV 113/115 LBIStPT. AFW LIES 577/578 m m . B.
C0lufMT P6E CWIFIRMED ADDITION OF NEW SUPPORTS TO VRVES MD PR0 VIED 1981 AllALYSIS. E011071 REPINtTS OVERSTRESS IN THIS PIP MALYSIS.
- ~~
1069 820315 FID ~ I 820511 TES DIR ECARDF VALVE LCV 113/115 UNSLFT. AFV LIlES 577/578 AUK. 3.
C019ENT: TES RECOMEDS THAT FILE 1069: REV.0, BE RESOLVED EXCLUSIVELY BASED ON TE REVIEW OF TE P6K 1981 MALYSISe P61E REASONS FOR TE CHA110ES MD THE ADDITION OF THE NEW SlFPORTS TO VALVES LCV113 MD LCV115 RATIER ThM CLOSED OUT AND TRAllSFERRED TO FILE 1071 FOR EVENTUAL RESOLUTION.
~~
1069 820315 'ifD~ ~ f 820517 R EA PER/A 55 RE VEVE LCV 113/115 IBISLPT. AFW LIlES 577/578 AUK. B.
C019EllT LACK OF SUPPORTS ON VEVE WERATOR CAUSES OVERSTRESS IN ECA PIPIll6 ANALYSIS 109. P6E IN PROCESS (F ADDIE SlfP ADDITI0llAL SUPPORTS TO K FIELD VERIFIED BY RLCA. RLCA 109 WAS KRull WITH SIPPORTS 011 VALVE WERATR (K15YCYF) TO S STESSES KLOW ELOWABLE. PGLE PIPING MALYSIS 2-4 DATED 1-16-82 ISICATE SLFPORTS ON VALVE (PERATW.
~~
1069 ~ E203T5 ~ilE ~~I 820607 Ti5 EE/i" i$iE EDF VALVE LCV 113/115 LIIStFT. AFV LIlES 577/578 AB. 3.
C0lvENT: PG1E PIPING ISO 447119e R.12 PIPING ANALYSES 2-14 (7/26/77 1 1/16/82). RLCA PIPIll6 AllALYSIS RLCA 109 SED. 6S K15UFU 1 K151CVF (3/19/82 1 5/9/82). PGE LTR. DCVP-RLCA-67 (4/23/02). PG1E DUG. 049264 SEETS 157-149. VERIF. AllEYSIS FAILS STRESS EDUATIONS DUE TO UNSLP. VALVE OPERATORS. TK ADDI. OF SUPT. ON VALVE OPERATOR RESILTS Ill ACCEPTABLE ST 1069 820315 FID ~ 5' 820630 TES ER/A N IE R E ifE' VALVE LCV 113/115 UllSLFT. AFW LIES 577/578 M . B.
COMENT: PG8E TO ADD SUPPORTS AND TO ASK VRVE SUPPLIER FOR VALVE QUALIFICATION FOR StFPORTS ON VALVE OPERATO 1069 ------820315 FID ----6 830625 TES DIR RLCA RDF _YES __ VALVE LCV 113/115 UNStFT. AFV LINES 577/578 AUI. B.
COMENT DCP COMPLETION SHEET DATED 830620 INDICATED THAT SUPPORTS HAVE BEEN ADDED TO AND VALVES 00ALIFICATI0il. HAVE BEEN QUALIFIED WITH THE SUFFORTS. RLCA TO VERIFY SLFFORT ADDITION MD R 1069 5i0ii5 ~iiE " I 830712 RICA FERE[Cl llE5 EDi IE5~ VALVE LCV 113/115 UNSUPT. AFW LINES COMENT: DCP COMP. SHEET DATED 830620 INDICATES THAT SUPPORTS HAVE BEEN ADDED TO LCV-113 AND LCV VALVES HAVE BEEN QUALIFIED WITH SUPPORTS. ELCA HAS FIELD VERIFIED ADDITION OF THESE SUPPORTS.
l -
1069 820315 FID 8 830715 TES PER/Cl TES liDF YES VALVE LCV 113/115 UNSUPT. AFW LINES 577/573 AUX. B.
COMENT: DCP COMP. SHEET DATED 830620 INDICATES THAT SUFPORTS HAVE BEEN ADDED TO LCV-113 AND L VALVES HAVE BEEN QUALIFIED WITH SUFFORTS. RLCA HAS FIELD VERIFIED ADDITION OF THESE StFPORTS.
1
~ 5E~ BE0ii5 'iiE "i 53E7i5 TE5 CE ~ EDEEEli TEE VALVE LCV 113/115 UNSUPT. FW L COMENT: PGIE AFW ISO 447119e R.2 SHOWS VALVES LCV-113 1 115 UNSUPPORTED. DCP COM SUPPORTS HAVE BEEN ADDED TO LCV-113 AND LCV-115 HAS FIELD VERIFIED ADDITION OF THESE SUFFORTS. Fl_iEVIOUSLY AN CLOSED ERROR VALVE CLASS A.
ITEM.
CPERATORS RLCA AND VALVES H
~
107E' 820M5 ~iiME ~0~ 820315 RECA 0IE ~ ~ RCA RBC ~ ~~
AUX.186. HORIZONTE SOIL SPRIll6 CALC.
COMENT: ITR-leFIST RLCA DIFFERS 3.1.4 THE AUXILIARY BUILDIN6 INiS/KlBE SOIL SPRIllG BT 50Z . RLCA TO C0lFLETE NCIEILL IRutK. TE let
~- -
"T07i~ 820F5 De 1 820721 RtCA PPRR/Ci WS TBC
- ~
COMENT! KLETE FROM ITR-1, 3.1.4 RCA KCONIESS THAT THIS FILE E COMBIIED WITHAux. nn6. NORIZONTAL Soll SrRIii6 EDI 1097.
REV 2 r3 REV. O LATEST REV. ACTION PG1E 83C817 0.3_El b FILE NO. DATE BASIS REY. DATE BY STATUS ORG TES MODS SUBJECT 1098 820714 ICD "5' E56955 TE5 ER7Ai" idiEE5i ~~ PiPiil5~REEVEUATION.
COMENT: BASED ON PG1E PRESENTATIONS OF THEIR TECHNICAL PROGRM, THIS FILE IS COMBINED WITH FRES 961, 1021, 1058 1059, 1060 AND 1104 AS AN ERROR CLASS A OR B. TE INCLUSION OF FRES 1060 AND 1104 INTO THIS FRE WAS ACHIEVED BT PRO REVIEW COMITTEE ACTION . EL CONCERNS OF THE ABOVE MENTIONED FILES WRL E REVIEED UNDER THIS FILE.
1098 820714 ICD ~ I 830120 Ti5 ER/AB I'GiE Itif ~ PIPING REEVALUATION.
COMENT BASED ON P61E PRESENT. OF TEIR TECitilCAL PR06RMe THIS FRE IS COMBIED W/FRES 961,1021,10581059106011104 AS M 1
ER A/B. TE INCLUSION OF FRES 1060 AND 1104 INTO THIS FRE WAS ACHIEVED BY PR00RM REVIG ComITTEE ACTION.El C 0F THE ABOVE ENTIONED FILES WRL BE REVIEWED HERE. REV 6 WAS ISSUED TO RERECT INCLUSION OF FRE 6001.
1098 820714 ~ ICD ~ f 830225 Ti5 ER/AB P5fE fil if5~ PIPING REEVALUATION.
COMENT: BASED ON PG1E PRESENT. OF THEIR TECH. PROGRAM, THIS FILE IS COMBINED W/FRES 961e1021:1058,1059,106011104 AS M ER/A/B TE INCL OF FRES 1060 1 1104 INTO THIS FILE WAS ACHIEVED BY PR06 REVIG COMITTEE ACTION. EL CONCERNS OF TE AB FRES WRL BE REVIEWED HERE. REV 6 WAS ISSUED TO RERECT INCL OF 6001.REV 7 ISSUED TO RERECT INCL OF 1115 1 60 1098 [2T7T4 'j{f 8 830627 TES ER/AB PG1E RDF YES FIPlHG REEVALUATION.
961,1021,1058,1059 1060 1 1104 AS AN ER/AB COMMENT: BASED ON PG1E FRESENT. OF THEIR TECH. PROGRAM, THIS FILE IS COMBINED W/ FILES THE INCL OF FRES 1060 1 1104 INTO THIS FILE WAS ACHIEVED BY PROG REVIEW COM ACTIO WILL BE REVIEWED HERE. REV 6 ISSUED 10 REFLECT INCL OF 6001. REV 7 ISSUED TO REFLECT INCL OF "I69E~ 59I4 TCE ' I 83E706 TE5 EUEFI EI1E Ri~F IEE FIEliG'REEVALUATICN.
COMMENT: BASED ON PSIE PRESENT. OF THEIR TECH. FROGRAM, THIS FILE IS COMBINED W/FRES 961,1021 1058 10*,9,1060 1 1104 AS AN ER/AB THE INCL OF FRES 1060 1 1104 INTO THIS FILE WAS ACHIEVED FY PROG REVIEW C03 ACTION. ALL CONCERNS OF THE AB WILL FE RFVIEWED HERE. REV 6 - INCL OF 6001. REV 7 ISSUED 10 RERECT INCL OF 1115 1 6002. REV. 8 - 1126. REV. 9 - 1 COMENT: SPACE RESERVED FOR LATER REVISIONS.
1098 0 11 0 COMENT: SPACE RESERVED FOR LATER REVISIONS.
~ ~
1099 820804 FID ~~ 820804 0 RLCA Diit" ~ ELCA PPit ~ COW 0ENT COOLING WATER EAT EXCH. TlttBINE EB8.
COMENT! DRAWING SHOWS 3/4' STIFFENER PLATES ON NORTH SIDE OF FIXED END SIFFORTi FIELD VERIFICATION DOES NOT SWW TESE PLATES ON HX 4 1-2.
~
1099 820804 ~ i ~1 Fl 820816 RtCA FfRR/0IP TES IER COMPONENT COOLING WATER EAT EXCH. RitBIE BLBS.
COMENT: P61E TO ESTABLISH 6EOM. CONSIDERED BT DES. MAL.1 DETERMINE REASONS FOR DIFFEREEES BETWEEN SUPPORTS.
1099 820804 FID ~~ 2 520020 TE5 PRR/OlP E65E EEE E0~ COMPONENT COOLING WATER EAT EXCH. TlftBINE bid 6.
COMENT: BASIS : TES REVIG OF GEOM. DIFF. W/ RLCA, REVIEW OF RLCA BASIS FOR FINDING (PGLE FRES) 1 REVIEW OF 1099-1 i TES MEMO 820819. PG1E TO ESTARISH TE SUPPORT CONFIGURATION REPRESENTED BY TE DESIGN ANALYSIS AND DETERMINE TE REASONS FOR TE DIFFERENCES BETWEEN THE TWO SUPPORTS.
1099 820804 FID ~i 821104 TES OIR IECA PPit - COMP 0ENT COOLING WATER IHT EXCH. TiltBIE E86.
COMENT: RLCA AND TES TO ASCERTAIN VEIDITY OF PG1E COMPLETION SEET AND VERIFY THAT TE ADBED PLATES OF CCWX 41-2 HAVE KEN DESIGNED FOR HOSGRI. DESIGN CALCS. FOR E TERNATE ' SHEAR RESTRAINT' HAVE BEEN FOUND IN PGLES RESPONSE TO TES RFI 0106 (DCVP - TES 418 DATED 821006).
1099 820804 FID 4 830216 RLCA PPRR/DEV TES PPR Ci 5dNT COOLING WATER EAT EXCH. TURBIE E86.
COMENT: P61E DRAWING 463683 REV. 6 SHOWS 3/4' STIFFNER PLATES ON NORTH SIDE OF FIXED SUPPORT. RLCA FIELD VERIFICATION S M S NORTH SIDE OF FIXED END SUPPORT OF HX 1-2 DOESN'T INCLUDE TESE. HX 1-1 DOES. DESIGN ANALYSIS NOT AFFECTEle SIRIFIEB l MODEL DOESN'T INCLUDE TESE RATES. DRAWING HAS BEEN REVISED.
1099 E56864 FID ~5' 830225 Tf5 PERI 6EE TfS PPE ~~ COMPONENT COOLING WATER EAT EXCH. TIRBIE ED6.
COMENT: PG1E DRAWING 463683 REV. 6 SHOWS 3/4' SilFFNER PLATES ON NORTH SIDE OF FIXED SUPPORT. RLCA FIELD VERIFICATION SMW$
NORTH SIDE OF FIXED EkD SLFFORT OF HX 1-2 DOESN'T INCLUDE THESE. HX 1-1 DOES. DES 16N ANALYSIS NOT AFFECTED: SIMPLIFIED i MODEL DOESN'T INCLUDE THESE PLATES. DRAWING HAS BEEN REVISED.
t __
1099 -- _ _820904 _ _ _ _FID _ _ _ __. 6 830225 TES CR -____ __NONE __ ____
PPR _____ COMPONENT COOLING WATER HEAT EXCH. TURBINE E 8 NO O COMENT: PG1E DRAWING 463483 REV. 6 SHOWS 3/4' 3TIFFNER PLATES ON NORTH SIDE OF FIXED SUPFORT. RLCA FIELD VERIFICATION SM US NORTN SIDE OF FIXED END SUPPORT OF HX 1-2 DOESN'T INCLUDE THESE. HX 1-1 DOES. DESIGN ANALYSIS NOT AFFECTEDe SIFL U MODEL DOESN'T INCLUDE TESE PLATES. DRAWING HAS BEEN REVISED. DEVIATION.
1100 820816 OD 0 820816 RLCA OIR RLCA RDC HLA SOIL REVIEW OUTDOOR WATER STORAGE TANKS.
COMMENT: RA FIELD LOG OF BORING t 11 (820208) INDICATES TWO FIREWATER TANKS I THERE SHOULD ONLY BE DE FIREWA
r--------------------------------------------------
LATEST REV. ACTION PG1E I b ,' M REV. O U HW /
DATE BASIS REV. DATE BY STATUS ORG_TES _ _ _ _ . MODS SUBJECT f/ILENO.
1120 850522 ~ii5~ T 830322 RiCA Pii75" Ti5 EE "~ 50NDEN50RSCR-35(PHASEIDCPCORRECTIVEACTION)
COMENT: DESION ANRYSIS HV-4.1 SHOWS 3/4' EXT. HOUSING MOUNTING BOLTS USED IN EARLIEP EDS CALC. ILV K 1/2'. IDVP FACTORED BOLT STRESS IN D.A. BY DIFFERENCE IN BOLT SIZE (3/4' VS.1/2'). RESIX. TANT BO RLOWABLE. DCP HAS REYlSED D.A. AS A RESULT OF IDVP FIELD VERIFICATION TO SHOW BOLT STRESS T
~'
1120 830322 FID 2 830405 Tl5 ER/B EGIE[E ~~ CONDENSORS CR-35 (PHASE I BCP CORRECTIVE ACTIM)
COMMENT: DESIGN MALYSIS SHOWS 3/4' EXTERIOR HOUSING MOUNTING BOLTS USED IN EARLIER EBS CRC WERE A PH I DCP CAD. IDVP FOUND 1/2' BOLTS MD FACTORED BOLT STRESS BY DIFFERENCE IN BOLT SIZE. STRESS EXCEEDS RLOWAKE. DCP HAS REVISED D.A. AND ABLE TO SHOW STRESSES BELOW ALLOWAKE.
~~
1120 830322 FID ~5~ 830420 TES DIR RiCA CE ~~ C55EiE50RSCR-35(PHASEIDCPCORRECTIVEACTION)
COMMENT: ADVERSE EFFECT OF LOWER BOLT SIZE ON STRESS COMPENSATED FOR BY INCREASED NLMBER ,
TES RECOMENDS RLCA TO REVIEW THIS FILE MD CONSIDER DOW6RADIN6 IT FROM AN ER/B TO M ER/C.
1120 830322 FID T 830429 RECA PER/C TIS E CONBENSORS CR-35 (PHASE I BCP CORRECTIVE ACTION)
COMENT: ORIGINAL EDS CALC SHOWED FOUR 3/4' MOUNTING BOLTS. FIELD W)WS 1/2'. HOWEVER, ABYERSE EFFECT OF SMALLER BOLT SIZE COMPENSATE BY ACTUAL FIELD CONF 16URAT10N (6 MOUN11N6S AS OPPOSED TO 4 IN DES 16N ANALYS DOWNGRADED FROM ER/B TO ER/C SINCE CRITERIA OR LIMITS HAVEN'T KEN EXCEEDED.
1120 830322 FID 3 830504 Ti5 ER/C 555E EIiK ~~ CONDENSORS CR-35 (PHASE I DCP ColeECTIVE ACTION)
COMENT: ORIGINAL EDS CALC SHOWED FOUR 3/4' MOUNTING BOLTS. FIELD SHOWS 1/2'. HOWEVER: ADVERSE EFFEC BOLT SIZE COMPENSATE BY ACTUAL FIELD CONFIGURATION (6 MOUNTINGS AS OPPOSED TO 4 IN DESIGN ANALYSIS)
DOWNGRADED FROM ER/B TO ER/C SlHCE CRITERIA OR LIMITS HAVEN'T BEEN EXCEEDED.
~
1120 5565fi T ii~ T 530567 Tf5 CR E6 E CE E6" C6R5fi50RSCR-35(PHASEIDCPCORkECTIVEACTION)
COMENT: ORIGINAL EDS CALC SHOED FOUR 3/4' MOUNTING BOLTS. FIELD SHOWS 1/2*. HOWEVER ADVERSE EFFECT OF SMM BOLT SIZE COMPENSATE BY ACTUAL FIELD CONF 16URAT10N (6 MOUNTINGS AS OPPOSED TO 4 IN DESIGN MRYSIS)
DOMGRADED FROM ER/B TO ER/C SINCE CRITERIA OR LIMITS HAVEN'T BEEN EXCEEDED.
~ ~
1121
~
830506 FID ~i 830506 RICA DIE ~ 'RLCA6IK ~iiliflZEeFILTERl B NIT-39 COMENT1 DESIGN ANALYSIS HV-5.11e R. O SHOWS ANCHOR BOLT SIZE OF 5/8' BETWEEN CONCRETE SLAB ANB WIK FLANGE Od BASE BEM. FIELD SHOWS 1/2' DIAETER. RLCA TG DETERMINE SIONIFICMCE. WILL K EXMIED W/1096 AND 1120 FOR POSSIBLE GENERIC CONCERN RE: HVAC COMPONENT HOLD DOWN BOLT SIZE.
~~ ~
1121 830506 FID T 830608 RICA PfRIC" Ti5 EE idi5fZEeFILTERIMIT-39.
COMENT: DCP REVISED ANALYSIS SHOWS BOLTS TO MEET ALLOWABLES AND ESIGN CRITERIA. RE9 ULT OF THIS EDIe GENERIC CONCERNe EVEN THOUGH NO OVERSIRESS. RLCA WILL REVIEW DCP BOLT SIZE PR06RM MD SPECIFIC SAlF HOLD-DOM BOLTS.
830506 FID ~ I 830610 T[5 ER/C i~GIE CE ~ ~ B3.T SIZE, FILTER TWIT - 39.
1121 COMENT: DCP REVISED ANALYSIS SHOWS BOLTS T0 hEET ALLOWABLES MD MSIGN CRITERIA. RESULT OF THIS EDI,1096 ANs 1020e PGlSIKE DEERIC CONCERNe EVEN THOUGH NO OVERSTPESS. RLCA WILL REVIEW DCP BOLT SIZE PROGRM AND IF BEEEB ECESSART, A SPECIFIC SMPLE OF.CL. I HOLD-DOWN BOLTS.
1121 556566 TfD~ ~5~ 5566i0 Tf5 Cf ~ 06EE CE E5~ 56LTSIZEeFILTERLMIT-39.
COMENT: DISCREPANCY BETWEEN HOLD-DOWN BOLT SIZE IN D.A. AND IN FIELD. DCP REVISED ANALYSIS SHOWS BG.TS TO EET A DESIGN CRITERIA. RESULT OF THIS E0le 1096 AND 1020, POSSIBLE GENERIC CONCERN, EVEN THOUGH NO OVERSTRESS. RLCA WILL REVIEW DCP BOLT SIZE PROGRAM AND IF ((EMFD NECESSARY, A SPECIFIC SMPLE OF CL. I HOLD-DOWN BOLTS.
~
1122 830512 OD ~0 830512 R[CA die ~~ ELCA 5 - LARGE BORE PIPE SUPPGtT 10/70SL COMENT: DES]GN ANALYSIS CALC NO. S-1281 R.3 DCESN'T ADDRESS SUPPORT FREQUENCIES IN UNRESTRAINED DIRECTIONS AS REQU LICENSING CRITERIA. SIMPLIFIED IDVP LALCS SHOWS FREQUENCIES LESS THAN 20 HZ. DCP INDICATES ANALYSIS HAS KEN RFVISED (REV 4) AND IT ADDRESSES AND SHOWS ALL FRE0. IN UNRESTRAINED DIRECTION CREATER THM 20 HZ. IDVP WILL VERIFY CKC
~
~Iii2" [3i5i2 ~iiII~ "i SiO653 RLCA PIE /I EE5 ~E - ((REE BORE PIPE SUFFORT 10/70SL COMENT: D.A. FOR SUPPORT 10/70SL (CALC S-1281, R. 3) DOESN'T ADDRESS SUFFORT FREQUENCY IN UNRESTRAINED DIRECTION AS REQUIRED BY DCP FROCEDURES. REALISTIC CALCS SHOW FRED TO BE AB0VE 20 HZ ALLOWABLE. IDVP DOESN'T CONSIDER THIS E01 TO BE A GENERIC CONCERN.
"iiM" 5i?5ih ~EI 7 550N6 RifA F1EE" I55 ~1EE - idPGFl0RE PIFT SUPPORT 10/70SL COMMENT: II. A. FOR SUFFORT (CALC S-1281, R. 3) D0f5N'T ADIRESS FRE0 OR STRESS IN UNRESTRAINED DIRECTIONS PER DCP FROCEDURES.
DEP FRITERI A IF0VIEES EITHEP FFf 0 EYCFED 20 H7 0F STFEcc. DDE 10 LOADING MEET Att0WAI<tES. DCP PEFFORhED FEM TO SHOW AtI. STFESSFS BELPW AllCWAFLE . If@f FFfi5 EDI N01 A GENFRIC CONCERN.
'tif 556'd) '6fI 5 55060 IES H Uii EGiE iM "" i RGilCFE FIF1 SUPPORT 10/70SL COMMFNT: D.A. FOR SUPPORT (CALC S-1281. R. 3) DnFSN'T ADDREC,S FRE0 OR STRESS IN W' GAINED DIRECTIONS PFR DCP PROCEDURES
/q DrP CRl1ERIA REOUIFFS FITHFR FREO NOT E4tFD 20CONCERN.HZ OR STFESS DUE-10 LOADING MEEf ALLOWAELES. TCP PE bl' All $1FESSFS PEI CW AltnuAFLE. IDVF FEU S EC1 A GENERIC
. . . . .1122. 830512 -..
_ _ . . _ DD _.
4 _ ....S30802 TES (k__ _ . --- ___NONE JFM NO ____ LAPGE
. _ _ _ BORE . PIPE SUPPORT 10/70SL rGhMENT! D.A. FCR Suf FORT (CALC S-1281. R. 3) DOEEri AD0RESS FRED OR STRESS IN UNRESTRAINED DIRECTIONS FER DCP PROCEDU DCP CRITERIA REQUIRES EITHER FPEG FyCEED 20 H1 OR STFESS PUE TO LOADING MEET ALL0uAFLES. DCPPERFORMEDFEMTOSH5W ALL SiitEEEFS EELOW Att0WABLE. :DVP FFE;c. E01 NCT A CENERIC CCNCEPN. DF VI ATION.
RLV 2 p REV. 0 LATEST REV. ACTION PGIE 830817 0.3-71 FILE NO. DATE BASIS REV. DATE BY STATUS OR6 TES MODS SUBICT 1122 0 5 0 COMENT! SPACE PROVIMD FOR LATER REVISIONS.
1123 830513 OD "6' 830513 RECA DIR EECA Ri5 ~~ INSTRUMENTATION TUBING SWPORT COMENT! ESIGN AMKYSIS ITS-5, R. O ASStBES SWPORT EMKR TO E A 1202 SECTION. D.A. ITS-5, R.1 PROVIE S AS-BUILT DATA THAT SHDWS A B 1202 SECTIDM. SIWLIFIED D.A. FOR SWPORT EMBER INDICATES STRESS ABOVE ALLOWABLE 1F C0RNECT SECTION PROPERTY (J) IS. USEB. REPRESENTS SOLE INSTANCE l&ERE LICENSING CRITERIA MM HAVE BEEN EXCEEMB.
"fif5" 830513 ~65 - i iiS6fi R R A Pfi1C~ ffi ifs - isifiURENTATION TUBING SUPPORT {
COMMENT! D.A. ITS-5 R. O ASSUMES SUPPORT MEMBER TO BE A 1202 SECTION. REYlSION 1 PROVIDES AS-BUILT DATA THAT SHOWS SUPFORT I MEME R TO FE A B 1202 SECTION. MORE REALISTIC CALCS SHOW ALL STRESSES TO BE UNDER ALLOWABLES. IDVP DOESN'T CON 51E R l THIS E01 TO BE A GENERIC CONCERN.
l
"[i25" E505i5 ~05" "i' 556657 TE5 EEIC"~ PGiERCE "" i5fEbEENTAT10HTUBINGSUPPORT COMMENT: DESIGN ANALYSIS ITS-5 R. O ASSUMES SUPPORT MEMBER TO BE A-1202 SECTION. R.10F CALC PROVIDES AS-BUILT DAit. THAT SHOWS SUPPORT MEMBER TO BE B-1202 SECTION. MORE REAllS11C CALCS SHl4 ALL STRESSES TO BE UNDER ALLOWABLES. THIS E01 NOTES A SOLE INSTANCE, IDVP DOESN'T CONSIDER THIS A GENERIC CONCERN.
556555 ~66" ~5',556fi5 Tf5 C5'~ ~ E05E RU s5- fi5fi0sENTATIONTUBINGSUPPORT l
"fi25" COMMENT: DESIGN ANALYSIS ITS-5 R. O ASSUMES SUFFORT MEMBER TO BE A-1202 SECTION. R. 1 0F CALC PROVIDES AS-BUILT DATA THAT I
l SHOWS SUFt0RT MEMBER TO BE B-1202 SECTION. MORE REALISTIC CALCS SHOW ALL STRESSES 10 PE UNDER ALLOWAPLES. THIS E01 NOTES A SOLE INSTANCF. If!VP DOFRN'T CONSIDER THIS A GENFRIC CnNrJRN. FRROR CL ASS C. l 1124 830514 OD 0 830514 RLCA DIR RLCA RDC AUXILIARY BUILDING SPECTRA GENERATION COMENT: D.A. F.E. MOEL C.R. SLAB USEB 10 GENERATE HOSGtt RESPONSE SPECTRA DOESN'T AGREE WITH FIELD LOCATION OF SWPORTING WALLS. SPAN LEETHS OF SLAB MAY SHIFT FREDENCY AND APPROACH FUNDAMENTAL VERTICAL FRE9ENCY AND PROVIE INCREASED AWLIFICATION. CLASSIFICATION OF E01 WILL DEPEND ON SUBSEQUENT YERIFICATION.
"{i2i" 8505ii 0D "i' 830627 RECA FEi7B" T'E5 R'DC AUXILIARY EUILDING SPECTRA GENERA 110N (3 COMMENT: DESIGN ANALYSIS FEM OF CR SLAB USED TO GENERATE HOSGRI SPECTRA DOESN'T AGREE WITH FIELD VERIFIED LOCATION OF
(') SUPPORTING WALLS. DCP REVISED FEP TO AGREE WITH FIELD. AT CERTAIN FREQUENCIES, SPECTRA INCREASED BY 15I. DCP INDICATES NO STRUCTURAL MODS RESULTED FROM THIS ER't0R.
1124 830514 OD 2 830628 TES ER/B PGIE RDC AUXILIARY BUILDING SPECTRA GEERATION COMMENT: DESIGN ANALYSIS FEM OF CR SLAB USED TO GENERATE HOSGRI SPECTRA DOESN'T AGREE WITH FIELD VERIFIED LOCATION OF i
UP'ORTING WALLS. DCP REVISED FEM TO ACREE WITH FIELD. AT CERTAIN FREQUENCIES, SPECTRA INCREASED BT 15I. DCP l ,,,
- CAlES NO STRUCTURAL MODS RESULTED FROM THIS ERROR.
1124 Ej55[4 ~66" "5 550I5[ T55 OiE ~ EECA (5C "" 5UiiLIERYBUILDlHGSPECTRAGENERATION COMMENT: DESIGN ANALYSIS FEM OF CR SLAB FOR HOSGRI SFECTRA DCESN'T AGREE W/ FIELD LOCATION CF SUFPCRTING WALLS. DCP HAS REVISED 10 AGREE W/ FIELD. SPECTRA INCREASES MOFE THAN 15% AT SOME FRED. ! WP DESIGN VERIFIED DCP SPECTPA. DCP INDICATES NO STRUCTURAL MCDS RESULT. PASED ON LETTER DCVP-TES-1252. RLCA TG REVIEW AND ISSUE A RESOLUTION.
I li}T' 555E4 'i)iI "E T3i)E2I REA PifRTCi IE5 IEC ~ EJTILihETBUILDINGSPECTRAGENERATION COMMENT: DESIGN ANALYSIS FEM OF CR SLAB FCR h0SGRI SPECTRA DOESN'T AGFEE W/ FIELD LOCATION OF SUPPORTING WALLS. DCP HAS REVISEL TO AGREE W/ FIELD. SPECTRA INCREASES MORE THAN 15% AT SOME FRE0. IDVP DESIGN VERIFIEP DCP SFECTRA. DCP INblCATES NO STRUCTUr(AL n0DS RE59LT.
ii}E~ i M 5ii 'i)E~ " I' ii3E755 TES FidOCI TE5 I<EC "" diIIilhRY IUILDING J SPECTRA GENERATION l C0enFNT: DESIGN ANALYSIS FEM OF CR SLAB FOR HGSGR! 5FECTRA 1:0ESN'T AGREE W/ FIELD LOCATION OF SUPPORTING WALLS. DCP HAS REVISED TO AGREE W/ FIELD. SPECTRA INCREASES MORE THAN 15% AT S0nE FREO. IDVP DESIGN VERIFIED DCP SPECTRA. DCP INDICATES NO STRUCTURAL M0bs RESULT.
~iif 855i4 Di" "I 85h5 TE5 CE ~ 5~0 E REC EE' IUElilhRYEUILDINGSFECTRAGENERATION COMENT: DESIGN ANALYSIS FEM 0F CR 3 LAB F0R HOSGRI SEECTRA 00ESN'T AGREE W/ FIELD LOCATION OF SUFFORTING WALLS. DCP HAS REVISED TO AGREE W/ FIELD. SFECTRA INCREASES MORE THAN 15% AT SOME FRE0. IDVP DESIGN VERIFIED DCP SFECTRA. DCP INDICATES NO STRUClVRAL MODS RESULT. FREVIOUSLY AN ERRGR CLASS B. CLOSED ITFM.
1125 830520 SID 0 830520 RLCA OIR R1CA CE HVAC COMPRESSOR CP-35 36 COMMENT: CONTROL AND APPLICATION OF HOSGRI SPECTRA WAS I KMTIFIED IN INITIAL SAW LE AS A GEERIC CONCERN. DCP CAP FGutE.ATED TO INCLUX REVIEW FOR CORRECT HDSGRI SPECTRA INPUTS. DESIGN ANALYSIS !>-HV-3.1-le REV. I USES INCGtECT AND IBICONSERVATIVE SPECTRA. NO OVERSTRESS.
~~
1125 830520 SID ~ T 830526 R EA PER/C TES 'CIIK HVAC C0WRESSOR CP-35, 36 COMMENT! CALC D4N-3.1-1 REV.1 USES INCORRECT AND UNCONSERVATIVE SPECTRA. CONTROL AND APPLICATION OF HOSORI SPECTRA IB Bt D
Q INITIAL SAMPLE WORK AS GEERIC CONCERN. DCP CAP FORMULATED TO INCLUDE REYlEV FOR CORRECT HOSGRI SPECTRA I WUTS.
THIS ITEM DOES NOT CAUSE OVERSTRESS.
rs
_j REV 2 fi30817 D.3-72a REV. O LATEST REV. ACTION PGIE FILE NO. '55fi ~ 5ASi5 REV. DATE BY SfEfb5' ERG TES~ MODS SUBJECT "iiif' 556555 IE5- "i~ 5566i5 T55 CR""~ 6ECEK 05 " EUAC'50fPLY FANS S-1, 2 COMENT: DCP FREQUENCY CALC USED ONLY BEARING BLOCK SUPPORT BEM AND NOT OTHER FLEX OF FAN SUPPORTING STRUCTURE. FN MAY ACTUALLY BE LOWER. DCP FRE0 CALC ACCEPTABLE - SIMILIAR TO INITIAL SAMPLE WORK (FAN S-31). DCP BEARING BLOCK SUPPORT BEM FRE0 CALC CORRECTS ORIGINAL RLCA CONCERN NOT VALID. CLOSED ITEM.
REV. O LATEST REV. ACTION. PG1E FILE N0. ~5Aff-"5A5f5 (i6I5Aff~~if-~5fAf65 dRG"if5~ MODS SUBJECT "fif5" 55555i ~if5~ "d' 55055i RLCA Off-~ ELTACEK ~~ SfAfi60BATTERYRACKS COMMENT: D. A. FOR RACKS ASSUMES 1/2' DIMETER A-307 STRUCTURAL BOLTS. RLCA FIELD VERIFIED BOLTS TO BE 3/8'. IF BOLTS THREADED AT SHEAR LOCATIONS SHEAR STRESS EXCEEDS ALLOWAFLES BY 631, IF NOT THREADED, STRESS IS ACCEPTABLE.
REV. O LATEST REV. ACTION PGIE FILE NO. ~6IIE "5A5i5 REY. DAIE~~EY- ~ 5iiFUT i@ i ~ili MODS SUBJECT "II3E' E3353i 'illi "i Bi$IO R[CA DIE ~ iiCA CIIK "" iihilhNBATTERYRACAS COMENT: D. A. F06 STATION BATTERY RACKS ASSUMES A-3071/2' STFUCTURAL BOLTS. RLCA FIELD VERIFIED BOLTS TO BE 3/8'.
D.A. ALSO DOESN'T CGNSIDER RESOLVED SHEAR FORCE FOR 3/8' BOLT ANALYSIS. STRESSES EXCEED ALLOWABLE IF CORRECT BOLT SIZE AND SHEAR FORCE IS USED.
REV. 0 LATEST REV. ACTION PGtE FILE NO. ~61iE'"liili ilI[.~iAIE BY STATiji DRE~i[F MODS SUBJECT "iiii' 53E5i3i ~ifi "i 53 i6 57 Ri~CA CERii/EIP TE5 EHI( "" STATIGN BATTERY RACKS OvENT: D.A. D.A.ALSOFOR DOESN'T STATION CONSIDER RESOLVEDBATTERY SHEAR FORCE RACKS FOR 3/8' BOLTASSUMES A-3071/2' ANALYSIS. STRESSES STRUCTURAL EXCEED ALLOWABLE IF BOLTS. RLCA FIEL CORRECT BOLT SIZE AND SHEAR FORCE IS USED.
REV. 0 LATEST REV. ACTION PG1E FILE NO. _____._______
DATE ____
BASIS ~_ _ _ _ _ _Bf REV.
DATE _ _ _ _STATUS
_ _ _ _ _ORG _ _ _TES _ _ _ _ _________ MODS SUBJECT "liis" COMENT: D .E533i A. FOR STATION " h OE5
'lii BATTERY TE5 Fisi)FP EGiECIiK "" 5}FTii)ItBATTERYRACKS RACKS ASSUMES A-307 1/2' STRUCTURAL BOLTS. RLCA FIELD VERIFIED BOLTS TO BE 3/8'.
D.A. ALSO ESESN'T CONSIDER RESOLVED SHEAR FORCE FOR 3/8' BOLT ANALYSIS. STRESSES EXCEED ALLOWABLE IF CCREECT BOLT SIZE MD SHEAR FORCE IS USED.
"ir8 ' 55055i 'fif 7 55055i Ti5 OIi-~~ (LEACEE ~~ 5iAfi60BATTERYRACES C0eENI: TES Ff OUESTS THA1 FLCA FEVIEW THIS FILE ALONG WITH THE DCP'S FESF0NSE TO RLCA FFI 1772 AND FROVIDE A RECOMCNIATI3N FOR ITE. F!ITNFE DIEF05I' ION.
Idi~ 55553{ TfD' ~5~ 556565 NIA FfFIC'~ if5 CEE ~~ 5fAfi6ABATTERYRACKS C03'ENT: [,ESIGN ANALYSIS FOR STATION BATTERY RActs (EGFM CALC D-E-3.4-1, R.0) LISTS DIFFERENT STRUCTURAL FRME BOLTS AND MCHOR PLTS TWAN THOSE IN THE FIELT!. ALSO LOAD DISIFIBUTIONS BTWN MEMEFS ARE UNCONSERVATIVE AND THE RESOLVED SHEAR FORCE
@ F0t.MF MI TS WAS NOT CONSIDERFD. RLCA HAS FERFORMED ALTEFNATE CALCS THAT SHOW ALL STRESSES MEET ALLOWABLES.
~
_.g__ _ . . .g __.__ _ _g . _ _ _ _g . ...... .__ ... .___ .____
COMEAi: SF ACED R1 SERVED FOR L ATER REVISION.
COMENT: SPACED RESERVED FOR LATER REVISION.
REV. O LATEST REV. ACTION PGIE FILE N0. '6AIE~5Aili lif."'lihii~~ii-~~5ihiiji i)Rf'ili MCDS SUBJECT
~
77-~ii27' 5iO[05 'UE ' " E 53i)E03 Ri~CA ole ~ iiCAJiit ~~ LARGE BORE PIPE SUPPORT 56S/3A
'_COMPENT: D.A. INCORRECTLY ANALYIED 1/4' WELD BETWEEN FIFE LUG AND SufPORTING STEEL. WELD STRESS EXCEEDS ALLOWABLE WHEN DIVIDED IdY WELD CROSS SECTION. SUPPORT MODIFIED BY DCP. CONFIGURATION QUALIFIED BY CALC NO LONGER EXISTS IN PLANT. NO CENEFIC CONCERN.
I
REV 2 O
0 830817 D. 3- 726 RIV. O LATEST FEV. ACTION PGIE FILE NO. lAlf 7 55i5 5Ef. ~ 6Afi ~ ~5 I 5idi65 655"fi5' MODS SUBJECT
" fin" 536663 ~65~ "i' 536626 RifA PiRIC" if5 Jid "" (EG5'50REPIPESUPPORT54S/3A COMENT WELD STRESS CALC USED CONSERVATIVE ASSUMPTION FOR MOMENT OF INERTIA. STRESS MEETS ALLOWABLES if ACCURATE MEMENT OF INERTIA IS USED AND RESULTANT STRESS IS DIVIIED BT WELD CROSS SECTION. SUPPORT MODIFIED BY DCP. SUPPORT 00ALIFIED BY CALC A-103, R5 NO LONGER EXISTS IN PLANT. NOT A GENERIC CONCERN.
REV. O LATEST REV. ACTION PGIE FILE NO. ~6Aff BASIS ifE ~~DATE BY ~~ 5fiilIS~ ORG TE5' MODS SUBJECT 1129 830603 OD 2 830627 TES ER/C PG1E JFM LARGE BORE PIPE SUPPORT 56S/3A COMMENT: D.A. MADE COMPENSATING ERRORS ANALYZING 1/4' WELD BETWEEN PIPE LUG AND SUPPORTING STEEL. WELD STRESSES DO NOT EXCEED ALLOWABLES. N0 GNERIC CONCERN. ERROR C.
REV. O LATEST REV. ACTION PG1E l
._ {
FILE NO. ____.DATE BASIS REV. DATE BY STATUS ORG TES MODS SUBJECT
, ~iif9" E3i6E3 OD ~ T T30T25 TlE5 CR IiOEE ' lit ~~ LARGE BORE PIPE SUPPORT 56S/3A COMENT: D.A. MADE COMPENSATING ERRORS ANALYZING 1/4' WELD BETWEEN PIPE LUG AND SUPPORTING STEEL. WELD STRESSES DO NOT EXCEED ALLOWABLES. NO GNERIC CONCERN. ERROR C.
REY. O LATEST REY. ACTION PGtE FILE NO. ~6AiE BASIS REV. DATE BY ~~ iEid5' S ORG TES' MODS SUBJECT 1130 830603 DD 0 830603 RLCA DIR FLCA PPR C65P605NT COOLING WATER LUBE OIL FILTER COMMENT: D.A. CiMCLUDES COOLER NOT GUALIFIED AND MODS ARE REQUIRED. PGIE PH. I FINAL REPORT STATES IT IS MD MODS NOT NEEDED. ,
ITR 48 R. O REQUIRES IDVP TO VERIFY DCP CAP HAS BEEN FULLY IMPLEMENTED. THE SIGNIFICANCE OF CONCERN IS THAT REQUIPED CORRECTIVE ACTION WAS NOT IMPLEMENTED. RLCA TO EXPAND REVIEW IN THIS AREA.
O REV. O LATEST REV. ACTION PGIE FILE NO. DATE BASIS REV. DATE BY STATUS ORG TES MODS SUBJECT
~~
"iE35~ [3E6E3 DD ' " I 830618 IIliA PERii[DIV Ti5 Iiit COMPONENT COOLING WATER LUBE DIL FILTER COMENT: DCP SCHEDULE MD FINAL REPORT SHOWED WORK ON THIS ITEM TO BE COMPLETE AND QUALIFIED. AFTER 830414 TECHNICAL MEETINGS DCP SHOWED THE ITEM INCLUDED ON INTERNAL INTERFACE LISTS OF ITEMS FOR ACTION. IT IS CLEAR THAT REQUIRED ACTION WOULD HAVE BEEN IMPLEMENTED. DCP COMITTED TO REVISE THIS SECTION OF PH. I FINAL REPORT.
REY. O LATEST REY. ACTION PGIE FILE N0; I['AII BASIS REV. DATE BY STATUS ORG TES MODS SUBJECT
~iE3E' T30IiO'3hi~ " F ii3Ii6Y7 tis F'RiRiIDEU i' Git iER ~~ COMPONENT COOLING WATER LUBE Olt FILTER COMMENT: PGIE PH. I FINAL REPORT INDICATES THIS ITEM OUALIFIED AND NO MODS. DESIGN ANALYSIS CONCLUDES THAT IT IS NOT G DUE TO HIGH N0ZZLE LOADS. DCP INTERNAL MEMOS INDICATE ITEM ALREADY BEING TRACKED. PH. I FINAL REPORT IS INCORitECT, FGIE HAS COMITED TO CORRECT IT.
REV. O LATEST REV. ACTION PGIE
^ 1135~ M63 ~ 6ti T EiO5i6 ii5 CR- E6EEfii 06~ C65f6AiNT COOLING WATER LUBE OIL FILTER 10 MENT: i.A. CMfttitU COOLER NOT OllALIFIED AND MODS ARE REQUIRED. PGtE PH. I FINAL REPORT STATES IT IS AND MODS NOT NEEDED.
MiP FW614 IECHNICAL MEETING. DCP SHOWED THE ITEM INCLUDED ON INTERNAL INTERFACE LISTS OF ITEMS FOR ACT!0N. IT IS rt M THAT PEOUIRED ACTION WOULD HAVE BEEN IMPLEMENTED. DCP COMITTED TO REVISE THIS SECTION OF PH. I flNAL REPORT. DFt FILE NO. DATE BASIS REY. DATE BY STATUS ORG TES MODS SUBJECT
~~
113i" 536566 ~6D~ ~6' 530606 RLCA OfR RLYAJfE (555~50REPIPESlFPORTS58S/16YAND63/26V COMENT: D.A. DO NOT EVALUATE SHEAR LUGS MD ATTACHMENT WELDS. EVALUATION REQUIRED FOR CAP. IDVP W CALCS AND EVALUATE THE LUGS AND WELDS BASED ON ORIGINAL LOADS.
REV. O LATEST REV. ACTION PGIE FILE NO. 'iIAiE'"IIfES IslD~ ~ EAiE BY STATUS ~ ORG TES MODS SUBJECT-O ~ E3E' 1 Ii3IIiOI5 ~0 iI' "E ii3E6E0 liLCA PERii/EEV TE5 ~5It ~~
Lj COMENT: DESIGN ANdYSES DON'T EVALUATE SHEAR LARGE BORE PIPE SUPPORTS 58S/16V AND 63/26V LUGS AND ATTACHMENT WELDS ECALCS H-1040 R.2 A BY DCP PROCEDURES. DEPARTURE FROM PROCEDURE, NOT ERROR. STRESSES AiE LOW BY INSPECTION.
L- _ _ _
REV 2 830817 D.3-72c O
U REV. O LATEST REV. AC110N PG1E FILE NO. 'idiE~555i5 E5E. "6Eii"~Ei 5fdfE5' 5EG~ if5' MODS SUBJECi 830606 OD 2 830624 TES PRR/DEV PG1E JFM LARGE BORE PIPE SUPPORTS 58S/16V MD 63/26V 1131 COMENT: D.A. FOR THESE SUPPORTS AND ASSOCIATED PIPING P0N'T EVALUATE SHEAR LUGS MD ATTACHMENT WEtDS.
REQUIRED BY DCP PROCEDURES. DEPARTURE FROM FROCEDURE, NOT AN ERROR. STRESSES IN THESE SHEAR LUGS AND ATTACHMENT WELDS ARE LOW BY INSFECTION.
REY. O LATEST REV. ACTION PGIE FILE N0. '6EIE BASIS REV. DATE BY STATUS ORG TE5' MODS- SUBJECT
" I555 " 830606 65" "i~ 5i56ii Ti5 Ci" ~ N6EEJiM "" E5E55'50REPIPESUPPORTS58S/16VAND63/26V COMENT: D.A. FOR THESE SUPPORTS AND ASSOCIATED PIPING DON'T EVALUATE SHEAR LUGS AND ATTACHMENT WELDS.
REQUIRED BY DCP PROCEDURES. DEPARTURE FROM PROCE N RE, NOT AN ERROR. STRESSES IN THESE SHEAR LUGS MD ATTACHMENT WELDS ARE LOW BY INSPECTION. DEVIAI10N.
REV. O LATEST REV. ACTION PG1E FILE NO. ~55fi ~ 5A5i5 ff6 ~ ~DATE BY SIAf65' ORG TES MODS SUBJECT
~~
"iiii" 856566 ~66" ~6' 830606 REfA OfE"" EECAE6C Adi[Ei4RYBUILDING COMENT: DCP REPORTED COMPLETION OF AUX BUILDING MEMBER EVALUATIONS. DOES NOT INCLUDE EVALUATION '!F SLA LOADING. -REQUIRED CORRECTIVE ACTION WAS NOT FULLY IMPLEMENTED, TET REPORTED AS COMPLETE. RLCA WILL CONTINUE REVIEW IN CIVIL / STRUCTURAL AREA.
FILE NO. DATE " EAlii REV. DATE BY STATUI ORG TES MODS SUBJECT "IE3I' Ii3E6E6 'iiD" "E E30I1Il R'LCA fi'if/CI TE5 iciC ~~ EEXEliRYBUILDING COMENT: THIS EDI CONTAINS AN INCORRECT STATEMENT. IT SHOULD READ "...THIS MODEL WAS REQUIRED TO MORE ACCLE DISTRIBUTE THE LOADS FROM THE ORIGINAL STICK N0tEL...' RLCA RECOMMENDS COMBINING THIS EDI WITH EDI 1097 AS AN ERROR CLASS A OR B.
REV. O LATEST REV. ACTION FG1E FILE N0. DATE B45i5 REV. DATE Bi ~ ~5fdf65~ 6i5 "i55' MODS SUBJECT
' 1132 556665 ~ 5 " "5' 556635 Tf5 PEEICi' fi5 E66 ~~ AUiitiiRYBUILDING COMENT: THIS EDI CONTAINS M INCORRECT STATEMENT. IT SHOULD READ '...THIS MODEL WAS REQUIRED TO MORE ACCUR DISTRIBUTE THE LOADS FROM THE ORIGlHAL STICK MODEL...' RLCA RECOMENDS COMBINING THIS E01 WITH E011097 AS AN ERROR CLASS A OR B.
REV. O LATEST REV. ACTION PG1E FILE N1. DATE BASIS REV. DATE BY STATU5' ORG TES MODS SUBJECT 1132 556565 OD "5' 830627 Tf5 CE'"" E6EE556 "" AUXILIARY BUILDING COMENT: DCP REPORTED COMPLETION OF AUX BUILDING MEMBER EVALUATIONS. DOES NOT INCLUDE EVALVATION OF SLABS THIS EDI CGNTAINS AN INC0 ERECT STATEMENT. IT EHOULD READ *...THIS MODEL WAS REQUIRED TO MORE ACCURATELY DISTR THE LOADS FROM THE ORIGINAL STICK MODEL...' RLCA RECOMENDS COMBINING THIS E01 WITH 1097 AS AN ER/AB. CLOSED I FEV. O LATEST REV. ACTION PGIE FILE NO. '65i5 ~ 555[5 ifE I 6Aff " ~ 5f " "5fEid5' 6RG TE5' MODS SUBJECT "fi35" 5506ii 'd6-~ ~6' 5566fi REfA DiR~ fEfA56F ~~ E555f'50REPIPING-ANALYSISSECT 8-117REV.2-COMMENT: VALVE 9003A IN D.A. 8-117e REV. 2 WAS MODELLED WITH 2/3 WEIGHT AT CVERALL VALVE C. OF G. 4.5.6.2 Or DCP PROCEDURE P-11 REV. 3 REQUIRES TOTAL VALVE WEIGHT 10 PE MODELLED THERE. RLCA TO EXMINE REV. 3 TO CONFIRM STRESS IMPACT AND CONTINUE REVIEW 0F VALVE MOIELLING.
REV. O LATEST REV. ACTION PG1E 1133 810611 CD . 1 830629 FLCA PER/C TES RDF LARGE BORE PIPING - ANALYSIS 8-117 REV. 2 C0nMENT: VALVE 9003A IN D.A. 8-117. R.2 WAS MODELLED WITH 2/3 WEIGHT AT C 0F G. DCP PROCEDURE REQUIRES TOTAL WEIGHT BE MOLEllED THERE. EtCA HAS VERIFIED ThAT REVISED DCP ANALYSIS CORRECTLY MODELS VALVE AND ACCELERATIONS MEET 4 LOL'A?! Et E01 1133 HAS EEEN C0hblNED INTO THIS FILE.
~ ~iih ~ 5 M 6fi ~65 ~ "J' 556f66 if5 EilC~ PEIEE6i "" LARGE BORE PIPING - ANALYSIS u ... . .
C0nnENT: D.A. E-117. R. 2 MODELLED 2/3 0F VALVE WEIGHT OF C. OF G. DCP PROCEDURES REQUIRES TOTAL VALVE WEIGHT. E01 1106 HAS EEEN COnBINED WITH THIS FILE. DCF HA3 REVISED ANALYSIS. RLCA HAS VERIFIED REVISED MALYSIS CORRECTLY M0CELS VALVE 9003A M D SHOWS ACCELERATIONS TO MEET ALLOWABLES.
O)
(' "iiji" Mhii 'di' "I 55706 T'El CDhMENT! D.A. 8-11b R. 2 MODEllED 2/3 0F VALVE WEIGHT OF C. OF G.
ri"" IIIEE i<if fiO" LARGE BORE PIPING - MALYSIS 8-117 REV. 2 DCP PROCEDURES REQUIRES TOTAL VALVE WEIGHT. EDI 1106 HAS EEf N COMBINED WITH THIS FILE. DCP HAS REVISED ANALYSIS. RLCA HAS VERIFIED REVISED ANALYSIS CORRECTLY MODELS VA'VF 90C3A MD EHDWS ACCFLERATIONS 10 hEET All0WAPLES. ERROR CLASS C.
I
D.3-72d REV. 0 LATEST REV. ACTIDH PGIE FILE h0. ~6dTE BASIS REV. DATE BY STATUS ORG TES MODS S11BJECT
~~
$i65i5 ~65 ~ ~6~ 556di5 REfA Ofi~~ NECAici I55C'5UCTANDDUCTSUPPORTS 1134 COMMENT: RLCA HAS REVIEWED 3 D.A. THAT USED STRUDL-II . IM 2 0F THE 3. LOADING RESULTED IN MODAL CORRESPONDING TO FIRST MODE. OhE DIRECTIONAL LOADING USED WITH RAYLEIGH-RITZ METHOD MAY ESTABLISH FIRST MODE FREQUENCY. POSSIBLE GENERIC CONCERN.
REV. O LATEST REV. ACTION PGIE a
FILE NO. DATE BASIS REV. DATE BY STATUS ORG TES MODS SUBJECT
~~
~~0 ~ 830616 RECA OIR RE5Ad5f EdE55~50REPIPINGANALYSIS2-120 1135 530616 OD COMMENT: VALVES LCV-113 AND 115 IN D. A. 2-120 REV. 0 WERE MODELLED WITH VALVE BODY WEIGHT OF 69 LBS A
- 119 LBS. RLCA. REVIEW SHOWED WEIGHTS TO BE APPR3XIMATELY 125 LBS A _ND 130 L 155 8505i5 ~E6 ~ ~[~ ijojig g[CA PEEIC~ TE5 Eif ~ ~ EEE55~50RE P! PIN 3 ANALYSIS 2-120 ENT D.A 2-120. R.0 MODELLED VALVE BODY WEIGHT OF 69 LBS A COMBINED INTO THIS FILE. _
- - MODELS_VRVES ANE SHOWS ACCELERATIONS MEET ALLOWARES. E011106
~~
LARGE BORE PIPING ANAL (SIS 2-120 "II55~ 5566i5 ~66 " " E 556765 Tf5 EE75 ~ f55EEEE 00hMENM D. A 2-120. R.0 MODELLED VALVE BODY WEIGHT OF 69 L MODELS VALVES AND SHOWS ACCELERATIONS MEET ALL0uABLES. EDI 1106 COMBINED 6" i3E55~50REPIPINGANALYSIS2-120 "ii55" 5556i6 ~6 f' "i" 850766 Ti5 CE~~ E6sEEDE COMENT: D. A 2-120. R.0 MORLLED VALVE BODY WEIGHT OF 69 LBS AN COMBINED INTO THIS FILE. ERROR CLASS C.
J MODELS, VALVES AND SHOWS ACCELERATIONS MEET ALLCU.4LES. E012106
~~
1136 830616 DMD ~If 830616 RE~CA DIR IEAifR COMPONENT COOLIN6 WATER SURGE TANK COMENT: ALLOWABLE CALCtLATED BOLT IN ANALYSIS STRESEES WITHIN IS LARGERCORRECT THAN ALLCJABLE ALLOWABLE. TANKDEFINED SHELL S EVALUATION OF TAMK SHELL STRESS AT N0ZILES.
ALLOWABLE IN FORMAL SENSE. IDVP FAULTED CONDITION EVAll)ATION SHOWED STRESSES WITH _ _
"fi5E~ 5566i6 DMD ~i~ 556650 RECA PER/C Ti5 EiE ~~ C6EE60ENTCOOLINGWATERSURGETANK COMENT: SHEAR ALLOWABLE STRESS IS USED. CALCULATED TA K INTERNAL IN ANALYSIS PRESSURE LARGER EXCLUDED THANFROMCODEEVALUATION ALLOW O VENTED TO ATMOSFHERE AND INTERNAL PRESSURE IS NEGLIGIBLE. ,
I
~
~ 1136" idO616 . iiME ~ E Ilio}Ii7 TES ER/C i'E1E 5ER ~~~ COMPONENT COOLING WATER SURGE TANK COMENT INCORRECT BOLT ALLOWABLE STRESS USED IN ANALYSIS. CALCULFTED STRESSES DON'T E01 ERRED W/ RESPECT TO INCLUSION OF DESIGN PRESSJRE CALC OF SHELL STRESSES NEXT TO N0ZZLE, ONLY 3 P t E FRESSURE IS REQUIRED (NEGLIG1BLE).
, ~
HONE PPR I4Ii' E0 iip 0I45NT COOLING WATER SURGE TANK 1136 830616 DMD 3 830707 TES CR ORIGINAL COMENT! INCORRECT BOLT ALLOWABLE STRESS USED IN ANALYSin. CALC Ff1SSURE IS REQUIRED (NEGLIGIPLE). ERROR CLASS~~ C.
0 830621 RLCA OIR IECAR5f LARGE BORE PIPING - ANALYSIS 4-101 830621 ~if 1137 D i: COMENT: VALVE FtV-365 IN REV.10F THE ANALYSIS WAS MODELLED WITH A WEIGHT OF 405 LBS. RLCA b TO BE APPROX. 502 LBS. COMBINES WITH 1133 AND 1115 AS A GENERIC CONCERN WITH VALVE LARGE BORE PIPING - ANALYSIS 4-101 ii5}" 83001 EED~ i~ 556T20 REUA P[E75~ W 5 EEE COMENT: VALVE FCV-365DCP MODELLED WITH REVISED ANALYSIS WEIGHT TO INCLUDE OFWEIGHT, EURRECT 405 LBS. RLCA LICENSING REVIEW CRITERIA SHOWED WEIGHT OF MEET. DCP d VALVE MODELLINS IN CAP.
COMITTED TO FINAL PIPING REVIEW TO ASSURE CORREN VALVE MODELLING. GENERIC CONCERN CO
-m 1137 fj6[ji ~js6~ ~5" 556765 T55 EETC~ SIEEEI ~~ LARGE BORE PIPING - ANALYSIS 4-101 VALVE FCV-365DCP MODELLED WITH TO ~WEIGHT OF 405 LBS. R. '.ACRITERIA REVIEW SHOWED W U'
COMENT: REVISED ANALYSIS NCLUDE CORRECT WEIGHT, LICENSING MEET. DCP AS ER/AB.
h d VALVE MODELLING IN CAP.COMITTED 10 FINAL PIPING REVIEW 10 ASSUR '
ii65EEEE 56~ [iE5550REPIPING-ANALYSIS 4-101
~~ j j j}" 5565}i ~6E6" " E 55 id5 Ti5 CR r'0MtHl1 VAtVF FCV-365 MODELLED WiiHCORRECTWEIGHT OF 405 LB!. R MEET.
CA DCPREVIEW S DCP REVISED ANALYSIE TO INCLUDE WEIGHT, LICENSING CRITERIA J
VALVE MODELLIWG 0 IN CAP.COMITIED T, FINAL PIPING REVIEW TO ASSURE LORREt 'T 3
i - -
- - - _ _ = m
,A
\'
PEV. O L ATEST REV. ACTION PGIE RlV I
. . . . _..a_._ 830817 J.3-73 flLL NO. DA4.. FASIS FFV. DATE . . .__.
BY . . STA1US
. _ . . . . ORG
. . . _ TES
_ . . M00S SUBJECT _
"i!5i' 83d725 ~diI "O~ 5367}~5 REUA 0}E ' Ei&AEEE ~ EIE6E~i(OREPIPING9-108,REV.O COMMENT! D.A. APPLIED SIF 0F 1.0 AT FIPE/ REGENERATIVE HX INTERFACE. RLCA DETERMINED SIF 0F 1.9 REQUIRED. PIPE STRESSES E ALLOWABLE IF CORRECT SIF USED. D.A. RERUN WITH USING ACTUAL SPECTRA, STRESSES MEET ALLOWABLES. DCP COMMITTED TO REVIEW ALL L.B. DESIGN CLASS I ANALYSES FOR SIF.
1139 556775 ~66 ~ ' T 5j6755 R[fA DIE ~ E((AEfQ ~~" 5sj(('j0RE SUFFORT 2159/'
COMMENT: D.A. FPE00ENCY CALC. IN RESTRAINED DIPECTION PERFORMED BY COMPARING COMPUTED SUPPORT DEFLE'CTION TO STANDARD DFFLECTION. CALC ERR 0NEOUSLY COMPAREDi RESULTS IN FREQ LESS THAN 20 HZ. REYlSED ANALYSIS HAS BEEN REPORTED TO SHOW CRITERIA HAS BEEN MET,
!!39 R30726 0D 1 830803 RLCA PER/C TES RCW SMALL BORE SUPPORT 2159/2 COMMENT: D.A. FREQUENCY CALC IN RESTRAINED DIRECTION BASED ON COMPUTING SUPPORT DEFLECTION AND COMPARING TO CONSERVATIVE STANDARD. DEFLECTION ERR 0NEDUSLY CONFARED RESULTING IN FRED. LESS THAN 20 HZ. DCP REVISED ANALYSIS AND RLCA VERIFIED THAL FEEG. EXCEEDS 20 HZ. AS-FUILT SUPPORT MEET LICENSING CRITERIA.
'li' 3I . 536f25 ~66~~ ~5' ii36569 T55 EEIC f5iEECU ~ 55 HEE'50RESUPPORT2159/2 COMMENT: D.A. FREQUENCY CALC IN RESTRAINED DIRECTION BASED ON COMPUTING SUFFORT DEFLECTION AND COMPARING TO CO STANDARD. DEFLECTION ERR 0NEOUSLY COMPARED RESULTING IN FRED. LESS THAN 20 HZ. DCP REVISED ANALYSIS AND RLCA VERiflED THAT FRED. EXCEEDS 20 HI. AS-Butti SUPPORT MEET LICENSING CRITERIA.
T{jf 5tif25 ~6iI ~ 3~ 5~36569 TE5 CE' ' A50EECU U6" 553EE'50RESUPPORT2159/2 CnMMENT: D.A. FREQUENCY CALC IN RESTRAINED DIPECTION BASED ON COMPUllNG SUPPORT DEFLECTION AND COMPARING TO CONSERVATIVE
~ STANDARD. DEFLECTION ERR 0NEOUSLY COMPARED RESULTING IN FREO. LESS THAN 20 HZ. DCP REVISED ANALYSIS AND RLCA VFRIFIED THAT FFFD. EXCEEDS 20 HZ. AS-BUTl1 SUPPORT MEET LICENSING CRITERIA. ERROR CLASS C.
"1146 536}29 'bli 1 556739 NCA OIE ^ 5ECA3[i ~' Ei55' IMP-CAPANALYSISSOE-7.1,EEV.O CnMMENT: DCP ANALYSIS DOESN'T EXAMINE DISCHARCE N0Z?tE FLANGED JOINT. IDVP REVIEW SHOWS COMBINAT10N OF SEISMIC PIPING N2ZILE LOADS AND DESIGN PPESSURE CAUSE FLANGE PDLT STRESS TO EXCEED ALLOWABLE CRITERIA (ASME SECT. III, CL. Ill W/HOSGRI CRITERIA).
"Sidd ~ P3532V ~66" "I' 5365ij MCA die" ' ELCA3Ci "" EiE5' PUMP-CAPANALYSISSOE-7.1,REV.O COMMENT; DCP ANALYSIS DOESN'T EXAMINE DISCHARGE N0ZZLE FLNGED JOINT. IDVP REVIEW SHOWS COMBINATION OF SEISMIC PIPING N0ZZLE LOADS AND DESIGN PRESSURE CAUSE FLANGE BOLT STPESS 10 EXCEED ALLOWABLE CRITERIA (ASME SECT. 111, CL. III W/HOSGRI CRIT.)
AHLICAIION OF AFPROP. CODE AND CALCS SHOW ALL STRESSES BELOW ALLOWABLE. AS-BUILT DOESN'T MEET PGIE PIPING SPECIFICAT "iii6" 556156 '65" T 556555 dCA FiUi" if5 3Ci ~ iiEE~ IMP-CAPANALYSISSOE-7.1,REV.O COMMENT: DCP ANALYSIS DOESN'T EXAMINE CISCHARGE N0ZZLE FLANGED JOINT. IDVP REVIEW SHOWS COMBINATION OF SEISMIC PIFING el0ZZLE LOADS AND DESIGN PRESSURE CAUSE FLANGE BOLT STRESS TO EXCEED ALLOWABLE CRITERIA (ASME SECT. Ill, CL. Ill W/HOSGRI CRIT.)~
AFPLICATION OF APPROP. CODE AND CALCS SHOW ALL STRESSES BELOW ALLOWABLE. AS-BUILT DOESN'T MEET PGIE PIPING SPECIFICATION "iiM" EiOIN 'dti" T 5555i5 Ti5 EUI F5iE3Ci "" fiE5'EOMP-CAPANALYSISSOE-7.1,REV.0 EnMMENT: DCP ANAlY919 DCESN'T EXAMINE DISCHARGE N0ZILE FLANGED JOINT. ID"P REVIEW SHCWS COMBINATI0n 0F SEISMIC PIPING N0ZILE 10ADR AND DESIGN PRESSURE CAUSE FLANGE BOLT STRESS 10 EXCEED ALLOWABLE CRITERIA (ASME SECT. III, CL, III W/HOSGRI CRIT.)
AFF1 tf ATICN OF APPROP. CODE AND CALC'i SHOW ALL STRESSFS BELOW ALLOWABLE. AS-BUILT DOESN'T MEET PGIE PIPING SPECIFICATION tt41 IdOS62 '06 0' 93686? RRA GIR ' NCA Eid ~ SM5d'hND LARGE B0PE PIPlHG COMMENT: DCP It0CEDURE P-11. R.4 DOEV'T INCillDE LINES 26 AND 1040 THRU 1043 HIGH ENERGY LINES FOR POSTULATED BREAK LOCATION REVIEW. SINCE P-Il DIDN'T IDENTIFY IINES AS H.E., POSTULATED BPEAK LOCATIONS MAY NOT HAVE BEEN !DENTIFIED.
!!42 830809 OD 0 830809 RLCA OIR RLCA RCW SMALL BORE SUPPORT SI-8R LINE 3900 COMMENT: ANCHOR SI-8R ON LINE 3900 NOT C0NSIDERED BY D. A. FOR EFFECTS OF VARIOUS LOADlING CONDITIONS ON OTHER D SUPPORTS. SUPPORT LOCATED ON NON-CL. I PIPING. CONSIDERATION OF VARIOUS LDADING CONDITIONS REQUIRED BY DCM M-9.
CONCERN HAS APPARENTLY EEEN ELIMINATED SINCE ANCHOR HAS BEEN REPLACED WITH A GRAVITY SUPPORT.
l i
REV 1 I REV. 0 LATEST REV. ACTION P6&E B30817 0.3-77 FILE NO. DATE BASIS REV. DATE BY STATUS OR6 TES MODS SUBKCT
~
7001 821011 QAR 'ii 821011 dit Olii"~ iiit EAit AUX ANO FH WILDING HNC SYSTEN COMNT: AS FAR AS COED E KTERMIEBe TERE IS NO EVIENCE W All INKPOSENT KVIEW W AUX ANO FH Ilf!L91NB HNC PRESOME LOSS CALC PERFORED BY GEZ, THIS ITEM IS OUTSIE CURRENT SEC SAWLE FOR IIVP PHASE 2.
7001 821011 QAR ~i 830202 TES PRR/CI IIS E - AUX AllB FH IUILt!E HNC SYSTEN COMENT: BASED UPON ADDITIONAL IEORMTION PROVIED BY P6K (BCVP-TES-647) ON 821215 AND REVIEED BY SEte TE CONCERN BY THIS FILE HAS BEEN RESOLVED. FILE TO K CLOSED.
7001 821011 ~i0 ~ E 830202 TES CR ~ iliR [ AUX All8 FH EUILBING HNC SYSTDI NONE COMNT AS FAR AS COULD E KTERMIED, TERE IS NO EVIENCE OF All IllIEPD8Elli KYlEW W AUX. AS FH KBS HNC PRESSWE LOSS CALC PERFWIMED BY GEZ. THIS ITjM IS OUTSIDE CURRENT SEC SAlPLE FOR llVP PH. II. tPON All. IE0 PROVIMS BY P688 (KVP-IIB 64h UN 921215 i RfVltW D If 8W Ce IE CONCERN AlsE 99Eb BY THIS FILE N SAT!sFACTORILY E90LVEB. FRE CLOIEl.
7002 Eii6fi ~iiWi~ ~6~ 821011 RiR DIR itiR $id ~ 66flIIIIBUT IT IRIll8EElli IMRD.F"4R; SECT.
C0KitT: NO OBICTIVE EVIDENCE FOUMB TMT T4 EFFECTS OF KT IMPINIDENT 011 C NTS N1tK Cllli 3.6 STATES TMT INil MS ACCOWLitKD. P0K CORD NQT P900KW ME AM ]T%'t. Jti d" lluitst GONTi MY 110T K IN CtflENT IDVP SCOPE. ADDITIONAL VERIFICATION UUIRLB.
~~~ ~~
7002 821011 OAR 1 821011 dit PPRR/0IP TES EAR CONTAlleHT KT IRINDEIENT C019pT P6E TO PROYlDE SEC W/0BICTIVE EVIDENCE AND/OR RESP 011SE RELATIVE TO AMLTSES FOR EFFECTS E KT INIldiDDT ON COMP 0E NTS INSI K CONTAll# H T PER PARA.3 6 0F FSAR.
~~
7002 821011 QAR ~i 821022 TES PRR/OlP ELE EAR CONTAll0HT IT Irll1 KENT COMMENT: PGlE TO PROVIK CALCtLATIONS AND OTER SUPPORTING 80CulENTATION OF KT IWINSEENT AllALYSIS PERFORIO INSIK CSITAllIDT '
AS STIPULATED IN FSAR SECT. 3.6e PARAGRAPH 3.6. ADDITIONAL VERIFICATION REQUIRED.
~ ~
7002 821011 QAR ~ Y 830204 TES Di'R- TES iWt CONTAlleOT KT IWIINEIElli O COMENT! JETVERIFICATION ADDITI0pl IRINGEENT lilSIDE PR00 RAM. THIS FILE CCitTAINMENT WILL E RECLASSIFIED AS AIS CLASS KillA/B6ERROR AllALYZED SO THAT IT CallBY DCP Allt K ABMESSES Ai! WILL E SU PART OF THE ADDITIONAL YERIFICATION EFFORT.
~i665~ 55i6ii QAR ~ I B30204 Tf5 ER/AB P55EEAR ~~ CONTAlleHT KT IrllEEIOT COMMENT: RFR AUDIT OF PGE SHOWED NO DOCUMENTED EVIBOICE RE. KT IMPINGDDT lilSIK CIBITAll0UT. FSAR SECT. 3.6 PAR. 3.6 STATES THIS WAS DONE. NECESSARY ANALYSIS KING DONE BY DCP WILL E REVIEED BT IDVP. FILE EFFORTS KSOt1EB IN ITM-34.
~~)35f' ili5II ~6AI ~ 5~ 536526 TE5 OiE~ 505CEIE ~~ C65iliUMENT JET IMPINEMENT COMMENT: SWEC TO REVIEW DCP COMPLETION SHEET. SIGNED B30720s AND FROVIDE A RECOMMENDATION FOR FliitJRE DISPOSITION.
~~ )55C- iftFli ~c iF ~ ~i~ 535555 Tii CE ~~ sesEsik EB~ C6siilsMENTJETIMP!NGEMEdi COMMEsT: JET IMPINGEMENT INSIDE CONTAINMENT ANALYZED BY DCP AND VERIFIED PY IDVP AS PART OF ADDITICNAL VERIFICATION ISSUAgrE OF ITP-48 PEPORTS SUCCESSFUL COMPLETION OF
- ADDITIONAL SAMPLE' COVERING JET IMPINGEMENT EFFORTS OF FOSTL' LATED FIPE RUPTURES INSIDE CONIAIPENT DEFINED BY ITR-34, SECTION 6. PREVIOUSLY AN ER/AB. CLOSED ITEM.
O
~f66 E ~ 82ii25 QAR ~ E 821123 COMMENT: REVIEW 0F TE.AlSTIFICAT10ll CONTAlleGT ISOLATI0ll SYSTEM THAT WAS EDS CINICURS WITH THE IIOT AVAILABLE. -
O REV. 0 LATEST REV. ACTION P01E R g308 D.3-118 FILE NO. DATE MSIS REV. DATE BY STATUS ORG TES MODS SU3 JECT 9064 830215 DMD 5 830407 TES PRR/DEV PGIE RRB AFW SYS COMPONENTS P0M 110s 111, 113, t 115 C0KNT P6tE RES. AND C0r. SNT. DATED B30322. ESIGN DOCUMENTS IFROPERLY REPORTED CLASSIFICATION OF P0M'S AS S-R. PGIE TO REVISE EWIRONMENTAL QUALIFICATION FILES AND INSTRUMENT SCEMTIC 102036 TO REFLECT CL. 11 STATUS.
~
8064 830215 CMD 6 830407 TES CR 'NONE itRB if0 ' AFW SYS COMPONENTS POM 110, lite 113, 1 115 COMENT: NO DOCKNTATION THAT P0M'S LISTED ARE EWIRONMENTALLY QUALIFIED. P61E RES. AND COMP. SHT. DATED 830322. DESIGN DOCUMENTS IFROPERLY REPORTED CLASSIFICATION OF POM'S AS S-R. POSE TO REVISE ENVIRONMENTAL QUALIFICATION FILES AND INSTRUENT SCEMTIC 102036 TO REFLECT CL.11 STATUS. DEVIATION.
8065 830608 FID ' T 830608 SEC OIR 5NC 5 ~ JET IMPINGEMENT RLVIEW C0KhT: POSTILATED DREAK DN FEEDWATER LINE NO. 555 MY IMPINGE UPON HORIZONTAL PORTION OF MIN STEAM LINE NO. 227. CONDUIT KX-582 MISIENTIFIED AND MY BE WITHIN ZONE OF INFLUENCE OF RCP OUTLET. LINE 24 MAY IMPINCE UPON CONDuli KX-429.
RtFilRE OF LETDmei LIE 24 MY IMPINGE UPON TWO 0F TE VERTICAL SUPPORTS FOR EXCESS LETDOWN LINE 24.
8065 830608 FID 'I '833AE8 SE C PPRR/OlP i5 5 ~~ "J5EiEPINGEMENTREVIEW COMNT: SAFETY EVALUATION SNOULD K PERFORMED BY TE DCP TO DETERMINE KTHER IDENTIFIED TARGETS ARE NEEDED TO SAFELY SHUTDOWN TE PLANT UNDER TE CONLITIONS ASSOCIATED WITH THE POSTULATED PIPE BREAKS OR RUPTURES.
8065 830600 FID 2 830616 TES PRR/0IP P61E LCN JET IMPINGEMENT REVIEW COMENT! FOLR ITDtS OF CONCERN HAVE KEN IENTIFIED RESULTING FROM DATA OBTAINED DURING THE IDVP 830524-26 SITE VERIFICATION.
DCP TO PERFORM A SAFETf EVALUATION TO RESOLVE TE ITEMS.
~56i5~ 830609 FID ~ 830621 T55 OIR 5EEC [EN ~~ JET IMPINGEMENT REVIEW CONGT: SWEC TO REVIEW TE DCP COMPLETIDH SEET SIGNED 830617 AND PROVIDE A RECOMENDATION FOR FUTURE DISPOSITION.
3065 _____ _____
830408 FID ____4 830715 SWEC PPRR/CI __TES LCN ___ JET IhPINDEMENT REVIEW OMMENT: DCP EVALUATED FOUR JET IMPINGEMENT INTERACTICN W/S-R TARGETS. ALL FOUR INTERACTICHS ARE CONCLUDED TO IM FUNCTIONS REQUIRED TO MITIGATE CONSEQUENCES OF POSTULATED HELB'S AND TO SAFELY SHUTDOWN PLANI. FOUR DISCREPAN CCNSIDERED ISOLATED INSTANCES AND NOT INDICATIVE OF ANY GENERIC DIFFICIENCY IN DCP JET IMPINGEMENT FIELD REVIEU.
8065" E30i'05 TIE ~ E E3E75 TI5 P5E/lE EE5 ((N ~~ JET IMPINGEMENT REVIEW OhMENT: DCP EVALUATED FOUR JET IMPINGEMENT INTERACTION W/S-R TARGETS. ALL FOUR INTERACTIONS ARE CONCLUDED 10 lhi AIR NO LSSENTIAL FUNCTIONS REQUIFED TO MITIGATE CONSEQUENCES OF FOSTULATED HELB'S AND TO SAFELY SHUTDOWN PLANT. FOUR DISCREPANCIES ARE CONSIDEFED ISOLATED IhSTANCES AND NOT INDICATIVE OF ANY GENERIC DIFFICIENCY IN DCP JET IMPINGEMENT FIELD REVIEW.
~~563E' E3E6E9 TIE " A~ 836I26 3 TE5 CE ~ ~~ E0EE I.CE C E0" JET IMPINGEMENT REVIEW COMMENT: DCP EVALUATED FOUR JET InPINGEMENT INTERACTION W/5-R TARGETS. ALL FOUR INTERACTIONS ARE CONCLUDED TO IMPAIR NO ESSENTIAL FUNCTIONS REQUIRED 10 MITIGATE CONSEQUENCES OF POSTULATED HELB'S AND TO SAFELY SHUTDOWN PLANT. FOUR DISCREPANCIES ARE CCNSIDERED ISCLATED INSTANCES AND NOT INDICATIVE OF ANY GENERIC DIFFICIENCY IN DCF JET IMPlHGMENT FIELD REVIEW. CI.
n v
"WT5:1 STh'NE I
ENGNEERING SERVCES V
E.1 ITRs In Numerical Sequence REV ISSUE ISSUED ITR NO. DATE BY TITLE 1 1 821022 RLCA Additional Verification and Additional Sampling (Phase 1) 2 0 820623 TES Comments on the R.F. Reedy, Inc., Qual-ity Assurance Audit Report on Safety-Related Activities ' Performed by PGandE Prior to June 1978 3 0 820716 RLCA Tanks 4 0 820723 RLCA Shake Table Testing 5 0 820819 RLCA Design Chain 6 0 820910 RLCA Auxiliary Building 7 0 820917 RLCA Electrical Raceway Supports-0 8 821005 RLCA Independent Design Verification Program l O for PGandE Corrective Action 9 0 821015 Development of the Service-Related Con-RFR l
tractor List for Non-Scismic Design Work Performed for DCNPP-1 Prior to June 1, 1978 10 0 821029 RLCA Verification of Design Analysis Hosgri Spectra 11 0 821102 TES PGandE-Westinghouse Seismic Interface Review 12 0 821105 RLCA Piping 13 0 821105 RLCA Soils - Intake Structure 14 2 830725 SWEC Verification of the Pressure, Tempera- l ture, Humidity, and Submergence Envi-ronments used for Safety-Related Equip-ment Specifications Outside Containment for Auxiliary Feedwater System and CRVP System O
O IDVP E.1-1 REV1 FINAL 830805
SPTF1 PTh'NE ENGINEERING SERVICES v
E.1 ITRs In Numerical Sequence (Continued)
REV ISSUE ISSUED ITR NO. DATE BY TITLE 15 0 821210 RLCA HVAC Duct and Supports Report 16 0 821208 RLCA Soils - Outdoor Water Storage Tanks 17 0 821214 RLCA Piping - Additional Samples 18 1 830524 SWEC Verification of the Fire Protection Provided for Auxiliary Feedwater System Control Room Ventilation and Pressuri-zation System Safety-Related Portion of the 4160V Electric System 19 0 821216 SWEC Verificatian of the Post-LOCA Portion of the Radiation Environments used for Safety-Related Equipment Specification Outside Containment for Auxiliary Feed-water System and Control Room Ventila-tion and Pressurization System 20 2 830725 SWEC Verification of the Mechanical / Nuclear l Design of the Control Room Ventilation and Pressurization System 21 1 830503 SWEC Verification of the Effects of High Energy Line Cracks and Modcrate Energy Line Breaks for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System 22 2 830725 SWEC Verification of the Mechanical / Nuclear l Portion of the Auxiliary Feedwater System 23 1 830527 SWEC Verification of High Energy Line Break and Internally Generated Missile Review Outside Containment for Auxiliary Feed-p water System and Control Room Ventila-tion and Pressurization System IDVP E.1-2 REV 2 FINAL 830805
"R TF1Fr?(NE ENGINEERING SERVICES O E1 ITRs In Numericei Sequeace (Coatia ed)
REV ISSUE ISSUED ITR N0. DATE BY TITLE 24 1 830504 SWEC Verification of the 4160V Safety-l Related Electrical Distribution System 25 1 830429 SWEC Verification of the Auxiliary Feedwater System Electrical Design 26 1 830502 SWEC Verification of the Control Room Venti-lation and Pressurization System Elec-trical Design 27 2 830725 SWEC Verification of the Instrument and Con-trol Design of the Auxiliary Feedwater System 28 830725 Verification of the Instrument and Con-2 SWEC l
trol Design of the Control Room Ventil-p" 29 0 ation and Pressurization System 820117 SWEC Design Chain - Initial Samples 30 0 830112 RLCA Small Bore Piping Report 31 830804 1 RLCA HVAC Components l-32 1 830401 RLCA Pumps 33 1 830428 RLCA Electrical Equipment Analysis 34 1 830324 SWEC Independent Design Verification of DCP Efforts by SWEC 35 0 830401 RLCA Independent Design Verification Program Verification Plan for DCP Activities 36 1 830620 SWEC Final Report on Construction Quality Assurance Evaluation of G.F. Atkinson 37 0 830223 RLCA Valves 38 2 830620 SWEC Final Report on Construction Quality Assurance Evaluation of Wismer and Becker 39 0 830225 RLCA Soils - Intake Structure Bearing n Capacity and Lateral Earth Pressure
(.)
IDVP E.1-3 REV 3 FINAL 830816
SeTri prh'NE ENGINEERING SERVICES l E.1 ITRs In Numerical Sequence (Continued)
(~)N REV ISSUE ISSUED ITR NO. DATE BY TITLE 40 0 830309 RLCA Soils Report - Intake Sliding Resistance 41 0 830419 RFR Corrective Action Program and Design Office Verification -
42 0 830415 RFR R.F. Reedy, Inc., Independent Design Verification Program Phase II Review and Audit of PGandE and Design Consul-tants for DCNPP-1 43 0 830414 RLCA Heat Exchangers 44 0 830415 RLCA Shake Table Test Mounting Class 1E Electrical Equipment 45 0 830517 SWEC Additional Verification of Redundancy of Equipment and Power Supplies in
(]) Shared Safety-Related Systems 46 0 830627 SWEC Additional Verification of Selection of System Design Pressure and Temperature and Differential Pressure Across Power-Operated Valves 47 0 830627 Additional Verification SWEC of Environ-mental Consequences of Postulated Pipe Ruptures Outside of Containment 48 0 830727 SWEC Additional Verification of Jet Impinge-ment Effects of Postulated Pipe Ruptures Inside Containment 49 0 830623 SWEC Additional Verification of Circuit Sep-aration and Single Failure Review of Safety-Related Electrical Equipment 50 0 830722 TES Containment Annulus Structure Vertical Seismic Evaluation g 51 TES Corrective Action - Containment Annulus C't U
IDVP E.1-4 FINAL REV 3 830811
'RTF1 RWNE l ENGNEERING SERVICES E.1 ITRs In Numerical Sequence (Continued)
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REV ISSUE ISSUED ITR N0. DATE BY TITLE 52 Replaced by ITR-68 53 Replaced by ITR-68 54 RLCA Corrective Action Containment Building 55 RLCA Corrective Action Auxiliary Building 56 RLCA Corrective Action Turbine Building 57 0 830801 RLCA Review of DCP Activities Fuel Handling Building 58 0 830808 RLCA Verification of DCP Activities Intake Structure 59 RLCA Corrective Action large Pipe Stress 60 RLCA Corrective Action Large and Small Bore Pipe Supports E 61 RLCA Corrective Ac' tion Small Bore Piping n 62 Combined with ITR-60 U
63 RLCA Corrective Action HVAC Ducts, Raceways, Instrument Tubing and Supports 64 Combined with ITR-63 65 RLCA Corrective Action Rupture Restraints 66 Combined with ITR-63 67 0 830812 RLCA Corrective Action Equipment 68 RLCA Verification of HLA Soils Work p
a IDVP E.1-5 REV 2 FINAL 830816
1%' F W NE ENGINEERING SERVICES E.2A ITR/E01 CROSS REFERENCE (O3 ITR E0I 16 968, 969, 970, 981, 1070, 1094, 1100, 1101, 3000 17 1009, 1098, 1104, 1106, 1107, 1108 18 8019, 8020, 8021, 8035, 8036, 8037, 8038, 8039 19 NONE 20 8012, 8016 21 8011, 8014, 8028, 8029, 8030, 8031, 8050 22 8009, 8010, 8015, 8027, 8048, 8060, 8062 23 8007, 8008, 8049 24 8013, 8022, 8023, 8024, 8025, 8026, 8045
- 25. 8011, 8042, 8043, 8044, 8061, 8063 26 8011, 8041, 8042, 8044, 8061 O
V 27 8018, 8032, 8047, 8049, 8051, 8052, 8054, 8055, 8057, 8058, 8059, 8060, 8064 28 8017, 8046, 8053, 8056, 8057, 8059 29 Design Chain - Non Seismic 30 1024, 1043 thru 1048, 1058, 1059 31 1018, 1061, 1083, 1096, 1102, 1120, and 1121 l 32 1020, 1022, 1072, 1073, 1113, 1114 33 949, 1004, 1006, 1007, 1008, 1087, 1117 34 Verification of DCP Efforts by SWEC 35 IOVP Verification Plan for DCP Activities by RLCA 36 9008, 9015, 9016, 9021 37 950, 998, 999, 1082, 1116 38 9001 thru 9007, 9009 thru 9014, 9017 thru 9020, 9022 thru 9029
{} 39 1112 IOVP E.2A-2 REV1 FINAL 830816
\
t 1%' F W NE ENGNEERING SERVCES O E.2A ITR/E01 CROSS REFERENCE ITR E0I 40 NONE 41 NONE 42 7001 thru 7006 43 978, 1088, 1099 44 1118, 1119 45 8012, 8016 46 8009, 8010, 8062 47 8001 48 7002, 8065 49 8017, 8057 50 1014 51 1014 52 See ITR-68 53 See ITR-68 54 1014 55 1028, 1097, 1124, 1132 56 1026 57 1092 58 1022 59 1098, 1126, 1133, 1135, 1138, 1141 60 1098, 1122, 1129, 1131, 1139, 1142 61 1098, 1141 O
IDVP E.2A-3 REV 2 FINAL 830816
'#PTF1 T-TT(NE ENGINEERING SERVICES Q E.2A ITR/E01 CROSS REFERENCE ITR E01 62 Combined with ITR-60 63 983, 1003, 1123, 1134 64 Combined with ITR-63 65 1098 66 Combined with ITR-63 l 67 1128, 1130, 1136, 1140 68 None O
NOTE:
The information on this Table excludes tabular material and appendixes.
10VP E.2A-4 REV 1 FINAL 830816
WTA m(NE.
ENGNEHtlNG SERVCES
() E.2B E01/ITR CROSS REFERENCE E01 ITR E01 ITR 910 7 971 None 920 6, 10 972 None '
930 7 973 None 931 12 974 None 932 12 975 None 933 12 976 10, 11 934 12 977 50, 51 935 12 978 10, 11, 43 936 12 979 None 937 12 980 58 938 12 981 2, 10, 13, 16 939 12 982 2 940 12 983 7, 10, 63 941 12 984 2 942 12 985 6 943 12 986 6, 10 944 12 987 6 945 12 988 58 946 12 989 56
(~'J
'- 947 12 990 6 948 12 991 6
~
949 33 992 2 950 37 993 2 951 12 994 2, 12 952 12 995 12 953 12 996 12 954 12 997 12 955 12 998 37 956 12 999 37 957 12 1000 12 958 12 1001 12 959 12 1002 10 960 12 1003 15, 63 961 12 1004 10, 11, 33 962 12 1005 4, 10 963 12 1006 33 964 12 1007 4, 10, 33 965 12 1008 10, 33 966 12 1009 2, 10, 12, 17 967 10 1010 2, 7, 10 968 2, 13, 16 1011 3, 10 969 2, 13, 16 1012 3 970 2, 13, 16 1013 4, 10 t I v
IDVP E.2B-1 REV 2 FINAL 830816 l
. o x
'A'F WNE ENGINEERING SERVCES E.2B E01/ITR CROSS REFERENCE
(~~)
v ,
E0I ITR E01 ITR 1014 2, 10, 12, 50, 51, 54 1057 12 1015 3, 10 1058 30 1016 None 1059 30 1017 3 1060 _12 1018 31 1061 31 1019 12 IUf2 10, 12 1020 10, 32 1063 10, 12 1021 12 1064 2 1022 2, 10, 32, 58 1065 2, 10 1023 12 1066 2 1024 30 1067 2 1025 10, 12 1068 2, 10 1026 7, 10, 56 1069 12 1027 2, 6 1070 -2, 5, 13, 16 1028 2, 6, 10, 55 1071 10, 12 1029 2, 6 1072 10, 32 '
1030 3 1073 32 1031 12 --
1074 10, 12 1032 12 IU75 12 fl 1033 None T076 12 1034 None 1077 15 1035 None 10/8 None ~
1036 None 1079 2, 6 1037 None .s 1080 10, 12 1038 None 1081 10, 12 1039 None 1082 37 1040 2 1083 31 1041 2 1084 10, 12 1042 2 1085- 10, 12 1043 30 1086 10, 12 1044 30 1087 33 1045 30 1088 43 1046 30 1089 None 1047 30 1090 None 1048 30 1091 6 1049 4, 10 1092 6, 57 1050 12 1093 - 6, 7, 10 1051 12 1094 13, 16 1052 2 1095 6 1053 3, 10 1096 31 -
1054 3 1097 6, 7, 10, 55 1055 10 1098 12, 17, 59, 60, 61 1056 None 1099 43-m
'~ ~
IDVP E.28-2' REV 2 FINAL 830816
x 1
L
! 7%V I W NE ENGNEERING SERVICES E.28 E01/ITR CROSS REFERENCE r]
v E01 ITR E0I ITR 1100 13, 16 3000 2, 12, 13, 16 1101 12, 13, 16 3001 2 1102 10, 31 3002 2 1103 10, 12 3003 2 1104 17 3004 2, 10 1105 12 3005 2, 10 1106 12, 17 3006 50, 51 1107 17 3007 50, 51 1108 17 3008 50, 51 1109 17 6001 59, 60, 61 1110 15 6002 65 1111 None 7001 42 1112 39 7002 42, 48 1113 32 7003 42 1114 32 7004 42 1115 60 7005 42 1116 37 7006 42 111/ 33 1118 44 (m) 1119 44 1120 67 1121 67 1122 60 1123 63 1124 55-1125 67 1126 59 1127 67 1128 67 1129 60 _
1130 67~
1131 60 1132 55 1133 59 "
1134 63 1135 59 1136 67 1137 59 1138 59 1139 60 1140 - 67 1141 59, 61 1142 60 (D
uj IDVP E.2B-3 REV 3 FINAL 830816
6 9g' F W NE ENGNEERING SERVICES I') E.3A ITR/ REPORT SECTION v
SECTION 4.0 ITR. SUBSECTIONS 42 4.1.3, 4.2.1, 4.2.2, 4.2.3 43 4.6.5 44 4.9.1 45 4.8.2 46 4.8.3 47 4.8.4 48 4.8.5 1 49 4.8.6 l 50~~ 4.4.5 Ti 4.4.5 52 See ITR-68 l 53 See ITR-68 l 54 4.4.4 1, 55 4.4.2 l 56 4.4.8 l 57 4.4.3 '
(~^; 58 4.4.6 V 59 4.5.2 60 4.S.2 61 4.5.3 62 See ITR-60 63 4.6.6 64 See ITR-63 65 4.9.3 66 See lil-63 67 4.6.2, 4.6.4, 4.6.5, 4.6.6, 4.6.7, 4.6.91 4.9.1 68 4.9.2 sg I D'iP E.3A-2 REV 2 FINAL 830816
W P W NE ENGNEERING SERVICES
(]) E.3B REPORT SECTION/ITR SECTION 4.0 SUBSECTIONS ITR Report Sections 0.0 through 3.7.3 have ,lo ITRs 4.0 None 4.1 None 4.1.1 None 4.1.2 None 4.1.3 11, 22, 42 4.1.4 5, 9, 29 1 4.1.5 5, 29 4.1.6 None 4.2 None 4.2.1 2, 9, 29, 36, 38, 41, 42" 4.2.2 2, 42 l
4.2.3 2, 10, 41, 42 1 4.2.4 36, 38 4.3 None 4.3.1 None 4.3.2 10, 41 7 4.3.3 None (d 4.3.4 None 4.4 None <
4.4.1 6 4.4.2 6, 55 4.4.3 57 4.4.4 54 4.4.5 50, 51 4.4.6 58 4.4.7 Nore 4.4.8 56 4.5 None 4.5.1 None 4.5.2 12, 17, 59, 60 4.5.3 30, 61 E6 None 4.6.1 None 4.6.2 3,-67 4.6.3 37 4.6.4 32, 67 4.6.5 43, 67 4.6.6 15, 31, 63, 67 4.6.7 33, 67 4.6.8 7, 63 4.6.9 67
~
- - m IOVP E.3B-1 REV 2 FINAL 830816
W F W NE ENGNEERING SEINICES U
F.1 ACRONYMS AND INITIALISMS AEC Atomic Energy Comission AFW AuxiliaryFeedwater(System)
AISC American Institute of Steel Construction AISI American Iron and Steel Institute ALDI Applicable Licensing Document Index ANC0 Applied Nucleonics Incorporated A*ll Authorized Nuclear Inspector ANS American Nuclear Society ANSI American National Standards Institute ASME American Society of Mechanical Engineers ASW Auxiliary Salt Water (Pump)
AWWA American Water Works Association Blume URS/ John A. Blume and Associates, Engineers l
BPC Bechtel Power Corporation f] CAP Corrective Action Program CCW Component Cooling Water (System)
CI Closed Item CMTR Certified Material Test Report COA Construction Quality Assurance CR Completion Report CRVP Control Room Ventilation and Pressurization (System)
DCM Design Criteria Memorandum DCNPP Diablo Canyon Nuclear Power Plant DCP Diablo Canyon Project (PGandE and BPC)
DDE Double Design Earthquake DE Design Earthquake DEV Deviation DF0T Diesel Fuel Oil Transfer DMD Design Methodology Deficiency l
D0P- Designated Other Parties D0V Design Office Verification
{} EDS IDVP EDS Nuclear, Inc.
F.1-1 REV1 FINAL 830805
l W F W NE EfGINEERING SEFNICES g3 EES Cygna Energy Services (formerly, Earthquake Engineering V
Services)
E0I Error or Open Item f
ER Error Report l ER/A Error Class A ER/B Error Class B ER/C Error Class C ER/D Error Class D ER/AB Error Class A or Class B FCV Flow Control Valve FID Field Inspection Deficiency F0T Fuel Oil Transfer (Pump)
FSAR Final Safety Analysis R:: port FT Flow Transmitter GEZ Garretson-Elmendorf-Zinov GFA Guy F. Atkinson Co. ~
GTAW Gas Tungsten Arc Welding HELB High Energy Line Break HELC High Energy Line Crack HLA Harding Lawson Associates HVAC Heating, Ventilation, and Air Conditioning (System)
I&C' Instrumentation & Control ICD Independent Calculation Deficiency IDVP Independent Design Verification Program IEEE Institute of Electronic & Electrical Engineers IGM ' Internally Generated Missile ITP Internal Technical Program (of the DCP)
ITR Interim Technical Report LCV Level Control Valve LOCA Loss-of-Coolant Accident MAFW Hotor Driven Auxiliary Feedwater (Pump)
MELB Moderate Energy Line Break MS Main Steam NCR Nonconformance Report NDE Non-Destructive Examination 7
U IDVP F.1-2 REV1 FINAL 830805
r I
i
] NEMA NFPA National Electrical Manufacturing Association National Fire Protection Association i
NPSH Net Positive Suction Head NPSHa Net Positive Suction Head available NQAM Nuclear Quality Assurance Manual (Bechtel)
NRC Nuclear Regulatory Consnission NRR Nuclear Reactor Regulation NSC Nuclear Service Corp.
NSSS Nuclear Steam Supply System 0D Other Deficiency OIP Open Item Transferred to PGandE OIR Open Item Report OWST Outdoor Water Storage Tanks PEI Project Engineering Instructions (DCP) l PER Po'tential Error Report PGandE Pacific Gas and Electric Company PMP Program Management Plan
] PPRR PRAP Potential Program Resolution Report Probabilistic Risk Assessment Programs PRR Program Gesolution Report PSRC Plant Staff Review Coninittee (PGandE)
QA Quality Assurance QAP Quality Assurance Program QAR Quality Assurance Audit & Review RCS Reactor Coolant System RFR Roger F. Reedy Inc.
RHR Residual Heat Removal RLCA Robert L. Cloud Associates RRA Radiation Research Associates SAT Spectral Acceleration Factors SIFPR Supplementary Information for Fire Protection Review SMAW Shield Metal Arc Weld SWEC Stone & Webster Engineering Corporation SWSQAP Stone & Webster Standard Nuclear Quality Assurance Pro-(~') gram IDVP F.1-3 REV 1 FINAL 830805
iPF WE ENGINEERING SERVICES TAFW Turbine-Drive Auxiliary Feedwater Pump TES Teledyne Engineering Services
{
TMI Three Mile Island I W&B Wismer & Becker Wyle Wyle Laboratories 1
O l
\
IDVP F.1-4 REV 0 FINAL 830805
-_ ___ _ - . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ . _ _ _ . _ _ _ _